ML19209B990

Reactor Restart Rept.

ML19209B990
Person / Time
Site:	05000077
Issue date:	08/09/1979
From:	Ebert D, Jordan E, Keene W CATHOLIC UNIV. OF AMERICA, WASHINGTON, DC
To:
Shared Package
ML19209B988	List: ML19209B987 ML19209B990
References
101, NUDOCS 7910110364
Download: ML19209B990 (19)

Text

. .

The Catholic University of America School of Engineering & Architecture Mechanical Engineering Department Reactor Restart Report AGN-201 Nuclear Reactor, Serial #101 Facility Operating License R-31 Docket 50-77 August 9, 1979 Dr. David D. Ebert Reactor Supervisor Mr. Varren E. Keene Radiation Safety Officer Dr. Edward D. Jordan Reactor Adminis trator

~

Dr. Yun C. Whang Chairman, Mechanical Engr. Dept.

79101103bY 1129 314 f

6 ABSTRACT J

This report presents the reactor restart procedures and results which verify that the reactor has been restarted and operated in accordance with the Facili ty Technical Specifications.

1 7 1 C.

l 1I /_

a .,/ _1J .

l 3

i.

Background and i n t rociuction The reactor was placed in the shutdown condition on February 22, 1975 and ..ot operated again until May 9,1979 Repair work was initiated on June 15,1978 by Dr. David Ebert and Mr. Vindsor Dempsey. Dr. Ebert received a Senior Reactor Operators License on January 17,1979 and the Reactor Operating License was extended for another 20 years on March 12, 1979(2 . Repai r and necessary paperwork to verify and docurent conformance to the new Technical Speci fications was complet 'd on May 8, .]j).

The rector was restarted on May 9,1979 following the approved Reactor Resta t Procedures (approved by the Reactor Safety Committee)(

In the subsequt nt months following restart, 1) a power calibration, 2) control rod calibrations, 3) measurement of k,x and, 4) verification of shut down margins were perf'ormed and observed to be both consistent with previously determined values and to conform with the Technical Specifi-cations. The reactor is now being operated on a routine basis, f% DN  :

1129 516

s De tai ls A. Prestartuo Maintenance and Surveillance The following list presents the prestartup items which were checked and verified to conform wi th the Technical Specifications.(2)

1. Shield tank level test and calibration

2. Shield tank temperature test and calibration 3 Seismic disalacement test and calibration

4. Thermal column water level check 5 Emergency lighting check

6. Channel I count rate, niateau, safety circui t calibration 7 Channel 2 level, period, safety circuit calibration

8. Channel 3 level, and safety circuit calibration 9 Visual inspection and leakage check

10. Control rod insertion and scram time calibration

11. Reactor scram from loss of electrical power

12. Radiation monitoring equipment calibration 13 Control rod drive inspection, l ubri ca tion

14. CUA Reactor Safety Corni ttee review of the startup procedure and the operating and emergency procedures 1IL/ 1 Jl/

i

B. Reactor Restart Procedures and Results

i. REACTOR RESTART PROCEDURES

1. Verify that all the maintenance and tests are in conformance wi th the Tech Specs. and have been carried out and documented.

2. Perform i tems 1-9a of the Prestartup Checkout Procedure, but leave the Cd foil inserted in the glory hole position.

3 Undertake a 1/M plot as SR #1 is inserted, es timating the cri tical posi tion of each step.

4. Assuming that the reactor is still subcritical wi th the SR #1 inserted, es timate the subcri tical neutron mul tiplication constant (k) under the condi tions that all rods are out of the core (ARO) and the Cd foil inserted.

This k will be K, ~ 11 A where R g is the ratio of the neutron detector t-Rt readings of SR #1 out to inserted (R < 1) .

y R; can be computed for each detector and applied, and then averaged and applied. A g is the assumed reactivity worth of SR #1 (N 0.0125).

5 KO should be less than 0.9654. This number is obtained by 1.0 t hex - N sgi

- pq = 1. 0 & O.mG MOtM4M

= oMGM This is the ARO shutdown k referenced to 20*C, assuming the Cd has no negative reactivi ty worth. If K is not <0.9654, s tep 6 should not be under-taker until the discrepancy is resolved. Return to the ARO condi tion. Record

6. all three neutron detector readings. Withdraw the Cd foil in approximately ,

I inch increments, performing 1/M calculations at each step. Al so, es tima te the reactivity worth of the change in Cd posi tion using the relation.

& 5 (I-ko l'Mo 1129 318

_4_

where R is the ratio of detector readings at the initial condition to the O

present posi tion of the Cd. k,46 should be less than approximately 0.9654 otherwise the estimates for SR and CR and/or k a re i n e r ro r, if this is not the case, Step 7 should not be undertaken until the descrepancy is resolved.

/. From the above information, assuming tha t the Cd foil has been removed, estimate and verify a. that the shutdown margin (wi thout Cd foil) is ?f Z Io h_

wi th the most reactive rod inserted; b. that the es tima ted k is 4. C . fo S 7o 0 k, c; that the reactor will be subcritical with the least reactive SR or CR wi tha . .a.

A.) . bsQ 2 o+ c.d veicy hsu-+ ysm s c.9 8 a ksia s o.%9 s-b) . l + hex E hs64 + 3 ( set \&A m or hex E ksw4 - 1 + o. ovt i Veidy he3 6 o.65 % Ak/h.

c').~tC.O.is sedis, bed,-fken c). d,l( be sdsMed tS ysu E o. o RS dbk

8. Provided that all the above condi tions have been satisfied or discrepancies resolved,1/M measurements should be undertaken as the SR #1 and 2 are inserted.

Af ter SR #1 has been inserted i t should be scrammed according to Prestartup Check 9b. Likewise, af ter SR #1 and 2 have been inserted they should be scrammed ,

according to Prestartup check 9c. -

9 Cri ticali ty should be achieved at the lowest practical power level since a power calibration has not been undertaken for 5 years (approximanly lW).

10. As soon as practical af ter the initial criticality, the following tests should be pe r fo rme d :

n' }

P00R OR nMAL

5-

a. Power Calibration

b. Control Rod Calibrations

c. Measurement of K ex

d. Verify that:

i. Shutdown margin 7f 2 7c with the most reactive rod inserted. -

11. The reactor would be subcritical with the least reactive CR or SR removed.

1129 320 4

II. Reactor Res tart Procedure Resul ts

1. Refer to the operations log 2&3 See Appendix A for copies of the appropriate sections of t!.e operations log. The pertinent data is put in tabular form in Table 1 and plotted in Figure 1.

~

4. k ,; 0.79 5 ko < 0 9654

6. See Table i and Figure 1.

aocd 2.73% auk ko + Ao cd = 0.82 < 0.9654 7.a) k shut = 0.8173 < 0 9675 b) k e .v

= - 0.1436 < 0.00065 c) Since b) is satisfied, so is c).

8. See Table 1 and Figure 1 and Appendix A 9 See Table I and Figure 1 and Appendix A. Criticality achieved at approximately It mW power on May S.1979

10. a) Power Calibration Resul ts:

Channel #1 = 584K cpm /100 mW Channel #2 = 114% / 100 mW Channel #3 = 4.: 3 x 10 ~3 Anps/100 mW These facto. s are consistent wi th those obtained in the past years of operation.

b) Control Rod Calibration Resul ts: 1 The integral rod worth for the fine control rod is given in ~

Figure 2. The total worth of the fine control rod was determined 0

to be 0.142% k and the dif ferential worth was measured to be 76 pp/cm in the linear region of the rance. The di f feren tial rod worth for the coarse control rod was determined to be. 607 pp/cm.

The total worth of the coarse control rod was inferred to be 0

1.14% k. These values are consistent wi th those obtained in the past years of cperation.

1129 521 i

c) k Calculation:

The excess reactivi ty at 20*C which would resul t if all the control and safety rods were inserted was determined to be Ak/ k.

0.435% This value is less than the Tech. Spec. limit 0

of 0.65% k and is consistent with the value obtained in -

the past years of operation.

d) 1. The shutdown mergin with the most reactive rod inserted at 20 5*C was determined to be -2.0% Ak/ k. The choice of 20.5*C was chosen because this was the lowes t temperature at which the reactor was operated since May 9,1979 This particular Limiting Condition for Operation (LCO) therefore defines the minimum temperature for operation when the glory hole is empty and the normal material in the Access Ports.

9 ii. The shut down margin wi th theleast reactive coarse or safety rod recoved and the other rods inserted was determined Ak/

to be -0.71% k at 20.5'C. This value is within the limits established by the Tech. Specs.

1129 322

References

1. Senior Operator License No. 3426, Docket No.55-667), January 17, 1979,

2. Amendment No.7 to the Facili ty Operating License No.R-31, Docket No.

50-77, March 12,1979

~

3 CUA Reactor Safety Committee Meeting Hinutes, May 2,1979 9

1129 323

TABLE 1 Inverse Mul tiplication Resul ts ondi tion Date & Page Ch 1 Ch 2 Ch 3 Ave

~

cpm 1/H  % 1/M x10 n,,

' 1/M 1/M

. A RO , C d i n 5/2/79 560 140 1.0 0.017 1.0 0.80 1.0 1.0

!. SR!1 In)Cd in 149 0 94 0.018 0.95 0.86 0 93 0 94

1. ARO, Cd Out 160 0.88 0.019 0.89 0 94 0.85 0.87 _

. ARO, Cd in .5/7/79 562 135 1.0 0.018 1.0 0.80 1.0 1.0

1. A RD , C d O u t " "

150 0 90 0.02 0 90 0 95 0.84 0.88

s. SR#1 In, Cd Out " "

200 0.68 0.023 0 78 1.15 0 70 0 72

i. SR#1 1 & 2 in.

Cd Out " "

250 0.54 0.04 0.45 1 90 0.42 0.47

. ARO, Cd in 5/9/79 565 150 1.0 0.018 1.0 0.85 1.0 1.0

1. ARO, Cd Out 175 0.86 0.018 1.0 0 95 0.89 0 92

3. SR#1 & 2 in cd out 290 0.52 0.032 0.56 19 0.45 0.51

5. SR!l & 2 In Cd Out, FR at 15 cm 300 0 50 0.038 0.47 2.0 0.43 0.47

7. " & C R a t 5 cm 320 0.47 0.04 0.45 2.4 0.35 0.42 3 " & CR at 10 cm 360 0.42 0.045 0.40 2.7 0 31 0.38

3. " & CR at 15 cm 490 0 31 0.073 0.25 4.2 0.20 0.25 10." & CR a t -;

17 5 cm 900 0.17 0.12 0.15 7.0 0.12 0.15 .

11." & CR at 19 0 1650 0.091 0.25 0.072 13.0 0.065 0.076-

.i." & CR at 20.0 cri tical 0 1129 324  ;

4 Fig. 1 Reactor S t artup 1/tt Plots .

1 . 0 o -- 1_.__ _.-_. 1. .-.. .t..:_,..

n- _ -:

.. .. ...._ . _.. ._ :-1

.t.. - . .l : . : .- . . --_:_n. .m. . _ 2, -_ ___ __. 4 .

.! .'.l * '

n--: =_:._.___.:_.._.

,.. _ _ . . _ . .:r... _*I..

.. . ._. . 1:

. a

. . ..g. .g. ... .

. .l.

.- .l .. _.

_ ._.... : ___-- ~ : I_n . z x .. .. ,

.__.g.._.._j~.._ q. g.

{;:n ***- .g*

_ . . . - . _-..-...._--.) _ - - . _ -- . .

_w ----.._~..___.._*..! l .,: : . .l..  ;: '

-- -- -~ = ~ = i =__E H  :  :

!!!E:T.G MhsdnelErl:.E:=: ':r- ----

0.9 ,____ .. . .. _ . . . _ .

i,r, ._.  : :l:. : .: 4. .-.. :_=. 4 ..: :. .r gan 3

n e . j u..q:. =.-. . _ _

--g . _ , .=. . . .... . ..._.. - . ...... ... ..

7-

?Ji .i -!!!EEi ii----sHfHidiiElEf3!:~ .

. ..::=.  : =: .n: :: =n ---: ::j :: , .. n - .

.. sn Av.n era :=n= c e =::-  :-

-  ::= n: ~ nn: r;. ::

'-- : n_ _ r:= . -

0.8 '

• n=_. 1 _ _. -*-

'.n"-._---~.~__~_~_.~.~.------

=-

m _

o 0 ..] =

m  ;

m ,,,,

~

e_e e

v 0.6

• y

~ "

r s --

x e

0.5 m

- ,~

r. -2 4 -

.o, _ _ _ _ _ . .= - -

w

r. ,

u r , 1 R 0.4

-,w-t 4

." !, za.

~

e _ . ~ - -_._f -

Y_ e

_e C -.

f 1

, 1-n cf. 3 x5 C

_a .

_. ~ i

' ~

0.2 '

f~~~ ^

, u- .

p

^

a t  ?.-..

' - $. ~

2 m_ ,

0.1

[.-------_._'.--g

^ -*

y;z-,;

-W - :- :_

q* --_,

=:

J g1 - - - -4 F

4

.d-(

!---- -~ ~~~~ i_ _tt . . ::~t.3_ E. __F/_d_f..v17.,._4:g5A_. - ---- ._:2. . .

-==_. _--

_n_ . ._=_:=__n._=_2..r__.

. n-

.1__ . . _ _

, . . _ . . _ _ , _ . _ _ _ . . _ - . _ . - _ _ _ . _ _ . _ _ . . _ - . -g. n _ _7. :'--- ----- :n- 1. ._ _ __-F -- _ g 0.0 1 2 3 *. 5 6 7 4 9 J pl l 12 n ,-.r Reactor Condition ( see Table 1) ): d 'q/ ) (.' "J

Fig. 2 Fine Control Rod Integral Worth Plot E,_ _

. y . . - - _- . .- -.

.._4.

l

* - ~- -* ' . } .-

.. .-4_. .. 3 .g;.,

. ...+

j- .. .. .,_,.------.-.-g,._

_j _

. d.

,___ ~ ._ _ .. . . .

~.~..~'~~---'~~+'..-,..C...T.-~.7 j ~~...

_.._.1 ~._-*

i ; - * .-. - ; --.- * , ;~_ *.'.. . l .--_ *_r_. ..'..

. . ,. ... ..._.n.__

[. 4_U_. . g . .- . . . . ., .. ._. . . .C.__-.- _. ._...

..m_ . .. .-- .- - . .

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

.g. . ..

. -+

- - . . - .. .._l..,..,.__._.

.. .. _ . . . ~ ._ _ . _ _ _ _ _ _ _ _ . . . _ _

~-

- . - - - . .__-_,=:==- '=-_

. 4-.

p .-

/( o--  : _ _ _

S..M-.

-e *

/b7 fAMX

~~ -

odW m o_.

m <N -.

M W r

[

v .Cg e *> $O a + -

u ,/

O l 3 /

>: 2 c= i

."- _ ,1' u, l Ob t.t

<a

.s -.>

G. <- l 4_

i /cco ~

T 1

1. E I

.e +-l

v. ris le i* T7 ,'"

d  : -

"S ,

-o ~l N

"} 0 0 -

j seW I1

$ M W, a#

=s '

C

_ *n ,

J W . -Ym ,/

v ,

=*= i ,

I O 5

,7 2 r .:

~e

/ ~

f 30D ,

A21l 0u - . . _ ,

= ~.__- *.-- ,,,y _

,4~

j fgn_ -wlp -

c 2

_ -4 <

,. =

44 -

_m. . _e e .. _.-- p M g '

~

- __.- 4 _qg ,  ; - ----

I ;~) ..-._.__.___-y

-~_._.._=_ _

___ g

_ - -+ - + - . . - - . _.

-1 1

s __ __.__. .__ _. ._..___._..._..- _ _ -"--_---.d, _

2. 4 G 8 to i z. i4 l (, IA 5o n 2c. 2 Fine Rod insertion ( c:n)

))2If 3' h

- Al -

[.coendix A page y g ~f AGil-201 Serial //101 Run # -

- Reactor Operations Log Date JN 79 Reactor Opera tor]([ r/ r. fn SeV SeniorReactorOperator,j4 r .,6 v /emt,7-Reason for Operation es s-r:JW //d d./A"C/V Authori zed Experiments mis Ale Sv.hzfro) Ob b/v-/hde ?::h Special Operating Limi tations A/57- <rw ,r-/ =b W L w be,' - 'b 's Shield %ter Temp ~erature /f, g/ (*C) Es timated Excess Reactivi ty (%Ak/k'.

Prestartup Checklist

1. All Reactor fleutron Detectors Workingy b . Channel 1: -

i. High vol tage #f# # (VDC)

'I. Zero check. /

2. Radia tion Survey:

Me ter type and number /IForc-; p-/ y_S ' .i . .i . Cal ibra te Jroo (cpm) iv. H gh level trap 93 (%fs)

Cal i bra tion // - S - 7T' //nm wr, L w level trip /o (%fs)

Max. survey reading ,t a/.c ens 2 /get., O#

3 f. . OP erate /</d (cpm) e loca tion 8E rw ,3,7

c. Channel 2:

L w level trip O.00/3(tfp) 3 Safety Feature Checks:  !

H gh level trip _/oo (%fp)

Thermal column seal [  !!! )

Manhole cover seal t/ !sv.i . trigh Cal . foo Zero check,o e/.//p%)

Access p crt fillers installed t/-

V: lPeriod

". Cal. .or gg)

Cd in glory hole / scram Ua ter temp. sui tch in place V-- V! t/ {mee) vi i . Opera te ,af / (%fp)

Skirt area OK /

d. Channel 3:

I. Zero check V

4. Area Radiation Moni tor Check' V .

Al a rm se tpoi n t ,7ma/y,. </. 2n: . /4 N: Cal i bra tion (. heck OK v ist. Lou level trip /d (%fs) y iv. High11cvel trip 93 (%fs) 5 Control Rod Drive Settings Check 2,f'3 v. Recorder OK '

vi. Operate,p h)

6.  !!carby Persons Informed / -

9 Rod Con'.rol Interlocks and Scrar-Checks:

7 Key in Console and Power On l/ /

a. Sequence interlocks OK V .

b. Safety 1 Scram Or' f~ i

8. Instrument Calibration and Level Tri P c. Safety I and 2 scram OK $-

Setpoints:

10. Cd Recoved f rom the Glory Hole

a. flo temporary wi ri ng ins talled (/ k

11. Calculate 3, Completed by W . Day?,gy Approved by T), d $

u l

.,,,i o r me r 01 .~

Tevie.<ed by, bk ,

Reac,or Supervisor

'[4,e3d Dat 3 / /91 11"~ '(27 100R ORG NA

- A2 -

Page l S C O

,(~ ACN-201; Serial ,1101

%' Run #

Reactor Operatior.s Log Date SYl/'77 Reactor Operator \)J. D% .- a, Senior Reactor Opera tor _ D.$ 6 Activity _

bhd [ Me m owce_ / hu - g h x

% } <A Ts.s0 %- W? .

TtME .

d DETA ILS b:30 CeuucI n ~f '

d.30 c% tut < afd . -

~

7 o I r th.

'ho:3 o y at cww en _

1<kV

_i M_ 4-- e N-^8. - 9at L a , 12c l a $s % W _ /

tt.4%

. 9,0' 3B T aeu 9 mMie e-b<I--

% n:ese (kpLJ aA- I_cc % m- w /

> n Ad$ nlL c. A0e-O ,

QQL ,P K.

'l1.07 l g [ s [2.

• l 2.l'1L SR'# d n s 'n i%dic# -

[/-f A/e# A 11;36

&n kowd S~ u Pet d .':

& .'43 LGAcl+rlw cd. -

@ &;z fc e fa f x VM Cd.1-kLA

-A R c 6 != L - ,

7 ed 2 r

c /s .3 i ARo CJL Mocy ( i .e e.on% Lc o.6oyicyi Lo A

%\ t sRm dL 1o $5 149 fc.9 4- c. o r8_ _

ARO b od

> o.4 0.9C o.TI a .9 4-

. 4 IGo c.$75 0.0\9h.C44 c . 94- c.qq o.8133 $

__w -

-- 2 i w, ~ , - pu -

f_ c . c o 2 s-

__ n ._

1-k ,

j =~c 7] 4.~ , J.,9(h.dJ.L~xeo,c)i i.s .

~ O ~ ' _E db ~$':

s ,seo = o.v,s. o n w ~ ~-

/

- A3 -

Page C 56I

, AGu-201: Serial #101 Run # -

) Reactor Operations Log Date fl w ,19")]

R'eactor Ope ra tor \Ah w bew Da 5 ,_ Senior Reactor Operator T>dl'D. 9L b k.

Reason for Operation $ 9 Af f. a  % ,

Authori zed Experiments cd ui, / i c h b G k 9 d 4di3 Special Operating Limi totions rNCab GAA.Nkhh

- a I

Shield Water Tenderature l 3.5 (*C) Es tima ted Excess Reactivi ty (% Ak/k,'

Pres tartus Check 1is t -

/

1. All Reactor. Neutron Detectors Vorking V b. Channel I:

i. Hich vol taae 99Cho (VDC) -

2. Radiation Survey: Y O  !!! ' '

!!e ter- type and number i~ !i i . Calibrate %CU (cpm) iv. High level trip D (%fs)

Calibration ll/'5hs- L.0 vlm(20 * ""1 J'P ( f5}

Max. s u r vey re'ad i n g .c-&. (c .1 m n Locatsoa ( 4 d J A. M _m ,//,4, ,

g #h s/

c. Channel 2: 44 1 L w level trip O.Oolf(Z p) 3 Safety Feature Checks: - ,  !

11 gh level trip /OO (%fp)

Thermal column seal /  !! _

eri

• )

cc p fi talled

v. L w Cal.'O.01 (%fp)

Cd in lory hole /

Vater emp. switch in place Period scram V!!i . Opera te 8.Olfitf p) / (--.-4 vi Skirt area OV vf ,1 . .-

. d. Char.nel 3,:_ _ -

44

' !:! Zero check & d

4. Area Radiation 11oni tor Check n ch ck OK V Alarm setpoint 6.-'l v e /lvt.:l( /00%

4 U.

.iJa. Lo..' level trip /c (%fs)

@ iv. High level trip 9( (%fs) 5 Control Rod Drive Settings Checkl5 4 v. Recorder OK v vi. Operate @ @ @ b 1;carby Persons informed '-

9 Rod Control Interlock and Scram

/ Checks:

7 rey in Console and Power On V ,

[

b. Safety 1 Scram OK

8. Instrument Calibration and Level Trip c. Sarct'/ 1 and 2 scram OK f 3 I

$ lE " **

10. Cd Removed from the Glory Hate a.

No temporary wiring installed p

11. Calculate excess i r, ,

Approved by O w d O . T h '-

Complete 3

_[ - _ 2 Lee x- S ~ 1 ~. _

'~

Pevicued by EU - ' ,

M% $ 16 f 77 Reactor Supervisor Date j /

1 1 "" '% 2 9 P00RORG,NA.

• A4 - '

Page # %2 AGM-201: Seria1 //l01 Run f -

t' ~ j Reactor Operation. Lo<t, Date N %

- lO" c

Reactor Operator W. D;m h Senior Reactor Operator h .

wh Activity h/to 61 h. -

U .

TIME -

DETAILS n:4L Cerl cmicf ,_/ J@ endo 2v3 IP 18 osa sq*'d Jmded aC9 18 b admom Cd Q

%~ ~ S t2"1 b$ b,r nwla ,$md ! ~ '

20:an '

x,.J L A M UNbno,U .

' T h.sz hmi 914 wM d ;_ ad3B so.u w 09a <%wn C) vol ARO O 'l% R o a.' d l w '

1 cL 1 ce.-

22 >_

- .cd 3

, Ax ARocJ.ed eso 1 <o.ot 1 oss- 2 1 2'3B sedikJ %h 2oc 1c.Ytd$$1 sic.97 LIE o.63- o, fsI 20.51 p n 2. h; Ci d as o 0 .6 h .c h 'o.. s lSo 1

bds o .SB O _ E flAA.- UsCbH MA GT_r AA rLneh .

i 1 os io-m~ge sed 26.madoA sLLAA 'i o o aaaawaA .

a

. - AS -

• Page f \~

AGil- 201 : Serial #101 Run // 6 ~;; .

Reactor Operations Loa Date P 4. I U'

Reactor Operator M hfrypf c s/ Senior Reactor Operato /h,,,3 ftfevt7 Reason for Operation /A/ /f 7/ ' f'r -/-/2,7"' // d Author! zed Experiments 8kegph d_cm,,v6 ;-f Ebp5nts;2/p // toc _c:~b u T Special Opera ting Limi tations b /th F~gdes /4" Mue-'/2.

Shield Mater Temperature yYd)5sYiinated Excess Reactivi ty , gep 7f ,'[ (%6k/k; g , - o ,. -

A .q$E Pres tartup Checklist -

.h c ddhm.k. 4,- -

1. All Reactor fleutroi Detectors Working / b. Channel 1:

i. High vol tage)400 (VDC)

2. Radiation St vey: /) ypa($1c-Wh ii. Zero check. ' __

He ter type and nut.ber fdm EfvrLe/r //J(

.i l i . Ca l i bra t ey,p 8 (cpm)

Calibration // 79' /ww' . i v. High level t r i p pfy/, (';fs )

Mcx. survey reading / 4~ pre-///e' v.

Low level trip fa Q (%fs)

Loca t I on b1?C;ei/t t'

. A/!E71- ' vi. Opera te /f tf) lcpmf

c. Channel 2:

3 Safety Fccture Checks: 1. Low level trip g fj_f,(%fp) j i High level Thermal colura seal ii. trip fianhole cover seal v/ iii. Ifigh Cal. V ~ s pei (%fp) /

Zero check [ (%fp) /ct. 'J o V

iv.

Access p crt filler stalled (%fp) . ooo/ '/b Cd in glory hole v. Low Cal. L, ' (5fjp , o f </e t!cter temp. switch .in plac - vi. Period scram , V (sec)

Skirt arca Ors y vii. Operate-V (tf9) ,o/# %

d. Channel 3:

4. Area Radia tion Moni to eck.l .i.

lii .

Zero check /

Alarm setpo,nt i Calibration check OK

('ii. Low level trip /'d T6i)_

. i 'v . High !cvel trip f7g (%fs) 5 Control Rod Orive Settings Check 7$ $ v. Recorder OK t/ _ /:v vi. Operate 1/ (%fs) ,gs~k/d

6. t;earby Persons informed 9 Rod Control Interlocks and Scrac 7 Key in Console end Power On Checks:

a. Sequence interlocks OK

8. b. Safety 1 Scram OK V I n s t r u:r.e n t Calibration and Level Trip ~

c. Safety l and 2 scram OK t/ i Setpoints: I

a. No temporary wiring installed /

/ 10. Cd Removed from the Glory Hole

, 11. Calculate excess [

Completed by ( i; W i f) $' 6 ~ Approved by_

/

_L t/

/

Senior Reac t or Opera te.-

Revie..ed by M _s W  ;!

Reactor Supervisor Da t e) 1129 331 P00RORBU.

- A6 - , . -Q ,h ^

Occrations Data -

h 1 b

4 fa%

I . Ini tial Control Rod Lower Limi t Posi tions: 2. Power Limit Instrument Readings:

f Fi ne control rod / 2--o (cm) Channel' 1 v i M cK (cpm) (I E

Coarse control rod pop 7 (cm) Channel 2 l"lO (%fp)

Channel 3 y $,o- i (amp) '

3. Channel Meter Readings f rom Neutron Source: . -

Channel All Rods Out

//I (cpm)

Only Safety Rods In

/ p.s' ,.:2 97)

1. 2 \%fp) 0/V

1. 3 tamp) < D3 %

, grX fp -' Y

/, gy/6 - / V

! Approach to Cri ticali ty /'O Y Cri ticali ty At trined /,9-o o '

(Time) (Time)

5. Power, Meter Readings, and Red Positions:

Time Channel'1 Channel 2 Channel 3 Fine Control Rod (cpm) (% power) (amp)

Coarse Control Rod (cm) (cmL -

,'n5 7 sw . 03 F '~ % she-' 'T /s'wo oc. 7 7(6W7 thffL 3.'> 0 , n a_ A3'o -i irM) rpD 26O , o Ib m Coo ie '1 c?.'7 h In''M /K",n r) seo e s &

/)/fn U90 D75 4 'l v to"T / D UO / <~, /0A L2'.3 90 0 - ! 2-  % v' !!~ ' M 6'Y -i? M M of k s"n

/l 1,n D

/ (,,5'C

/ 9- K r '2- S~

/t N'%

/. 75/O If l 7 ~ D hr % C' '

/ 9'0 xD

~4 $. _G' /D -'Il __ , d'~ ^ St*Mco clo , es t) p.~1 . ,

9 -/n /( _ -/o G */b 7 Kth-1/ /44 5 9 ~

er

,_) o , u r-)

l i

l l i

6. Remarks Tima ~Fd~ - f5"n n. we b M i n t rt- hc.si7 i o 5 (D ' 'W f-0. - Uk_w L.:-fsm,-n i m W dW M. Ihw .,

}'~~C. /.S'd-in / M' d2 h Olk(

f o r v LL GC- m '

/~/, M ftf n ic 27f:3

/n & Iv'1 -

.t n f 'fL o, f 5~ C- m -

gG n. (L r

/ 2. @ /Ln1 1b Cl'2L /9.nb'(btK

'i C> f (7. *

% ent)O'A l . ' '

(I < S 0I'" ' "" " (' '

' l' 4 e in~ lWO ' % <M,K1 W5 ud ,

j ,$ / 1 C f/1 kuts 44 S Cl'4 r A_- I l 4 t

Pftnn re p g Nk Eh inL .._

7. Shutdown Check list.

a. Manner /M o t .Yi., - c. Recorder s tandby/of f

b. All rods dcwn f. Ccn'; ole and s ki r t dcors locked

c. Console pcwcr off g. Kays returned to SRC2h 3 2 .-s ij-

_d. Cd in glory hole a b c Time l djcifJglCn ITc~i9i) ~Ch 2 Tfp) Ch 3 (arps) Ini t i7 ' - [ELS _ hb a w V _N/ L 1 Y___/ (, D C]_J e9fjo # iD

i. i}}