IR 05000443/1987017
| ML20236H177 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 10/19/1987 |
| From: | Barber G, Keller R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20236H157 | List: |
| References | |
| 50-443-87-17OL, NUDOCS 8711030496 | |
| Download: ML20236H177 (34) | |
Text
- _ - _ _ _ _ ._ . __ _ _ _ . - _ _ _ -
- e
- q
?n
....
< r
.
U.S. NUCLEAR REGULATORY COMMISSION'
REGION I j Requalification
. Examination Report'N ; 50-443/87-17(0L);
Facili.ty: Docke't N Facility License N NPF-56 Licensee: Public Service Company of New Hampshire d q
Post Office Box f330- < 1 J
q
'
Manchester, New Hampshire._03105 - j
Facility Name: Seabrook Nuclear Generating" Station'-
Examination At: Seabrook; Nuclear Generatin'g Station:-
.
., Examination Dates: July 28-30,1987 a" Chief; Examiner: 8/4fI' 4 @ fM' -S$B M-/k87J d G. S. Barber, Rea( . Engi neer . ( Exami ner),
.
.Date 1 Approved By: ) Yk/rft '
R. M. Keller, ChiefI, PWR Section .Date-Operations Branch '
Division of Reactor Safety
.
]1 Summary: Written and operating. requalificationTexaminations .were :given ;to eight licensed Senior Reactor.-Operators. Five of- the L eight senior reactor ;
operators passed all portions of.the examinatio .
h i
Q10$5 v
Skln ..
-
~.
_ t
-. ._
- l
. j
'I 2- 1
- i
.i 1. Summary of generic weaknesses noted from grading the written examination This . information 'is being provided to document areas of. weakness ' which - u should aid ,in upgrading requalification ' training. No reply is require .j
?
Senior Reactor Operators .I Question N '
I 5.01a Explanation of how and. why MTC ' changes in an overmoderated core -1 as temperature is increased, i 5.02c- The effect of varying rod speeds on the power level reached at
- criticalit .05b Differences between the RAT ~ breaker synchronizing check relays and the UAT and EDG synchronizing ~ check relays and why the differences are necessar .07a Two automatic actions that occur if flow in any EFW system feed line reaches 450 gpm and the reasons for these action .02b Actions required when a rod from a shutdown bank drops into the i Cor .
7.03a Trip breaker and control rod status on initial criticality heatu .04 Plant response to operator errors that resulted . in LERs: during Mode 5 operation .07 Three actions required to enter an RCA without an RW .01a Knowledge that a transient which will result in ERG E-1 imple-mentation should be classified as a site area. emergenc .05b The proper actions to be taken if plant conditions will not allow access to a lock that had been compromise .06b Knowledge that TS surveillance requirements do not have to be met on inoperable equipmen .07c The minimum number of licensed operators necessary on shift for safe shutdow .08a&b The conditions that must be met to allow deviations from written 1 procedure _ _ _ _ _ - _ _ _ - -
_
,
'
- .
1 ,
!
3 ,
y q
I Summary of generic weaknesses 'noted from the' operating examinations-
' .
This information is being provided to : document .: areas of weakness 'which should aid in upgrading requalification training. No reply ' is, require Ogretor Weaknesses Coordination' between board operators during manipulations of 'CVCS, Rod Control, the turbine and SGWLC ' during _startup with ' a ' positive j moderator temperature coefficient were ineffectiv Manual operation of fee'd water regulating valves' and. their bypasses j at various p'ower levels was deficien Understanding of ' controller j operation was lacking, Major components and instrumentation that would be: affected by a ;
loss of vital AC were not understoo i Simulator Weaknesses )
i The plant page did not work in the simulator, i
,
'
.< The RVLIS System was inoperabl .{
l The I/O override function cannot override an SI signa il 1 The I/O override functions cannot be limited to automati ; Most of the malfunctions are limited to only one component or instru-ment allowing the operators to predict failed components, j l Modeling for a steamline break and steam generator (S/G) tube rupture l was questionable. During the steamline break, level stabilized at a '
minimum level and the S/G did not completely blow dow During the S/G tube rupture, level oscillated widely when the steamlines were i
,
filled with wate '
l l 3. Personnel Present at Exit Interview:
!
NRC Personnel G. S. Barber, Reactor Engineer (Examiner)
E. Yachimiak, Reactor Engineer (Examiner)
D. Ruscitto, Resident Inspector NRC Contractor Personnel P. Isaksen, EG&G, Examiner ,
B. Picker, EG&G, Examiner W. S. Roesener, EG&G, Examiner i
l
_ - _ _ _ _ _ _ . - _ _ _ - _ _ . _ - _ .A
m
_ _ _ - _ _
,
.
4'
,
Facility Personnel
'D. Moody, Station Manager-J. Grillo, Assistant Operations Manager P. Richardson, Training Manager R. J. Hanley, Operations Training, Supervisor L. Carlsen, Senior. Simulator Instructor W. J. Temple, Licensing Coordinator Summary of NRC Comments Made at Exit Interview:
The chief examiner presented'the number and type of examinations conducted during the previous week. In addition, generic weaknesses noted from observation of the operating examinations were also presented. ..The chief examiner stated that there were unnecessary personnel in the control room
.
during the examination A tour group and operator candidates for an upcoming initial examination were in the control room at the . time of the oral examination Examination Review A review of the written examination was conducted immediately following the examinatio Facility comments were discu'ssed on 'a line item. basi The number of facility comments was minimal, and were resolved to the satisfaction of the chief examiner and the license Attachment: Requalification Written Examination and Answer Key (SRO)
l i
i
____ _ ___ ___ _A
..
_ _ _ _ _ - - _ , _ _ _ .__ _ _ __ _ _ _ = _ _ _ _ _ , _ _ . _
- .,___ ._ _ _ , __ __ .. .. _ _. .
,
~ '
c
'
,
yjyhyp& **!;Yl !f'
Y
_
_
' '
s
. MTa ' .b +
+
,
'
. U.15. s NUCLEAR : REGUCA' TORY? COMMISSIUN .
~
i *
.
i' ,
. SENIOR REACTOR OPERATOR'REQUALIFICATION-EXAMINATION" m
~
'
,
FACILITY i '
.
USEABROOK 1 -
. _ - ~ . m . :;
. .- ..-
,
,
-
., .. , <
_ REACTOR'TYPEti ._PWR-WEC4 3 ___,,m, , , , _
'
^
D A T E A D M I N I S T E R E D : "_ _8 _7./ _ 0 _7 _/.2. 8._'...
_- _- .- - - - _ ~ , , _ -. . . . .-w
.
- .
xEXAMINER: . --BARB
- - - .E. .Ri .' . S . _ ~ _.. _ . A -Tn J- n. ;.
--- - - , ,c. .
.
E CANDIDATE: ;_______,_.,._,_.;._____;__J
, ,
,
'
.
, .
. .. . . .
' '
P JN@lRUCIJQN@_JQ_C9NQJpSIE: . .
o
. Read'the attached; instruction pageucarefu119.' Thi's examination; irepl[$ces the current cycle: ; facility . administered requalification examinatio ,
'Retrainirig . requi rements . f orm f ail ure iof'
'
thistexaminationLare the. sam'e:Las'
for failure of a requali f i cati on' ex'aminati on' p'repa'r.ediand radmini stered by; 4 4,
=yourl s training staf . Poi nts'- for each. questi on 7 : are: ' indicated 3 fin! >
l-parentheses after the.; questio The passing-gradefrequires atYleast.170% '
in each category and a final grade of-at'.least 80%". Examination papers".Oq will be-picked up.four'(4T hours afterJthe. examination starts.- '
-
m
'
I%UDF ,
'
CATEGOPY % OF CANDIDATE'S LATEGORY . , ,
,
_-_SC_ ORE' -'VALUE . CATEGORY
.
__V_ALUE - T_OT_AL_ - ------- - - - - - , . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
_lh g9__ _2h99 ____.____ _
_ .__.,_ 5. . THEORY OF'.NUCLEARLPOWERJPLANT!
OPERATION, FLUIDS,'AND;
>
i THERMODYNAMICS lh99 _ 39499 ._.,______ -_;-_4 PLANTLSYSTEMS'DESIGNE CONTROL',
/AND -INSTRUMENTATION 1 r .
l
, i ,
_.1h 99-_ _2h 99 _ _ _ _ _ _ , . _ .
_,,.____.__'7.'. . PROCEDURES 7-; NORMAL' iABNORMAL', ,
EMERGENCY AND' RADIOLOGICAL:
CONTROL 7 "K l' _lh 99__ 2h p9 , _ _ _ _ _ _ . _ _ , _ ____._ ' ADMIN 151RATIVE PROCEDURES,,
CONDITIONS,.AND LIMITATIONS-3 9.:.99 _ _ _ _ - _ _ _ _ _ _______% Totals Final Grade
,
All work done on thi s ex aminati on: i s my ow I have,neither gi.ve '
l' '
'-
nor received aid.' .c s
--.:-----_.--:--.__ z _-; '
Candidate's Signature
).]
1-
% f q?
-
'
ls L
,....< <
. . . s
., ,
.
A .
~
NRC RULES AND GUIDELINES'FOR LICENSE EXAMINATION ~. During the administration of this examination the f ollowing rules apply:
. Cheati ng on the examination' means an automatic denial of'your applicatio '
and'could result in more severe penalties.- _; Restroom trips are to be limited and only-one candidate at a timefmay leav .You must avoid all contacts with anyone outside the examination room to avoid even'the appearance or possibility of cheatin ' Use black ink or dark _ pencil gnly to ' facilitate legible reproduction . Print your name in the blank provided en the cover sheet of the examinatio . Fill in the date on the cover sheet of the examination 1(if necessary). Use only the paper provided for answer Print your name in the upper right-hand corner of the first.page'of eat,h l
l 7.
I section of the answer sheet.
l (. Consecutively number each answer' sheet, write "End of Category __" as appropriate, start each category on a new page, write gnly gn gne pide of,the paper, and write "Last Page" on the last answer. shee . Number each answer as to category and number, for example, l '. 4 , . Skip at least three lines between each answer, 11. Separate answer sheets from pad and place finished answer sheetsfface l down on your desk or tabl . Use abbreviations only if they are commonly used in facility literatur . The point value for each question'is indicated in parentheses aft'er the question and can be used as a guide for the' depth of answer require . Show all calculations, methods, or' assumptions used to obtain an answer to mathematical problems whether indicated in the question or'not.
l 15. Partial credit may be give Therefore,' ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLAN . If parts of the examination are not clear as to intent, ask questions of the examiner onl . 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 assistance"irt completing the examinatio This must be done after the examination has been complete .
. _ _ _ _ _ _ _ _ _ _ . - - - - - _ _ _ - _ - - _ .-_ - _ . ,
-
-.- ..
.
'.
,
--- 18. When.you complete pour examination,.you shall:
,-
~
a. Assemb1 e. your examination as .f ollows:
,
(1)- -Exam questions on to (2). Exam aids - figures,1 tables, et (3)' Answer pages including figures which'are part of the answer'.
b. Turn in your copy of the, examination and all pages'use6 to. answer the examination. question c. Turn .in all- scrap paper and;the balance of . the paper that' you . di'd !
not use fortanswering'the question <
~
l l d. Leave the examination area, as defined by-the examiner. -If after I leaving,.you are found'in this area'while the examination is still l in progress, your license.may.be denied or revoked.
L l
l I
l l
l l
l l
l.
l
,
l
.!
i
') .
l
l
'
-I
l- -.
-:- --_
j
- ,
- 5'i__IHEgRY[OE_NgCLE@S_POWEF;PLANJ_OPEB9119N1 _ FLUIDS,_9Np PAGE 2
_
'
'- IHEBMODYN8MICS
.
.
QUESTION 5.01- (2.00)
Answer the following questions' concerning :coef fici ents ' of reactivit How and why;does ihe value of MTC change as ' temperature i s increased in an overmoderated core ? (0.75) Which initial temperature,58 F or 557 F, will give'the largest change'in the magnitude'of MTC as boron concentration is lowered from 1000=to SOO-ppm ? BRIEFLY EXPLAIN WHY , (0.75) WHY does power defect become more negative as the core-ages 1? (0. 5) -
QUESTION 5.02 (2.00)
Consider two separate startups for physics. testing. Assume the.only1 l difference between the two is that.during startup: #1 rod speed'is twice as l
during startup #2. Qualitatively COMPARE.the difference between.the two startups with regard to the following:
I (The time of rod pulls and time between rod pulls are the'same.)
l Critical rod height Time to criticality Power level at criticality Startup Rate just prior to criticality QUESTION 5.03 (1.60)
Assuming you are operating at 857. power indicate how the following changes in plant conditions would affect DNBR (increase, decrease, remain constant). Consider'each' case separately'and assume l control systems are in automati The operator withdraws control rods without changing turbine loa . Steam Generator safety falls ope Pressurizer heaters are inadvertently lef t o Reactor coolant pump speed decreases.
l l
l (***** CATEGORY 05 CONTINUED ON NEXT.PAGE *****)
t-l:
E_--___-- l
. Sl__ISEgBy_gE_ NUCLE @B_E9WES_Eb@NI_9EE09IJgN_f6U]D@f_@ND 1 PAGE 3
^* IHEgggDYN@g]Cp
', i l
,
QUESTION 5.04 (2.00) 1 Explain why AFD tends to continue to' increase in the positive direction after a power reduction. Assume no rod motio !
I How would the Xenon oscillation resultino f rom. the f ollowing two cases I be different? Explai l i
1. A turbine runback occurs with rods in aut Rods drive l in 60 step . Rods are driven in 60 steps' starting from the same initial position as in Case 1, but are slowly driven in ove four day QUESTION 5.05 (2.25) !
.
-
J If reactor power is increased f rom 75 to 100%, HOW (INCREASE, DECREASE-or REMAIN THE SAME) will differential rod worth change for each of.the I following condition Consider each separately and justif y each response j with a brief explanatio j d Rod position and boron concentration .are held constant, Tavg is allowed ;
to decrease Rod position held constant, boron concentration diluted to maintain f Tavg constant Boron concentration is held constant, rods are withdrawn towards their upper limit to maintain Tavg constant
,
I
l
,
l l
,
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
_. - _ _-_ w
-- - PAGE 4:
. 5,__lUEOBy_OE_ NUCLE 98._EOWES_PL9NI_ OPE 8@ TION 1 _ELVIDS 3 _9ND N
,
"
T
- -HERM..O.DYN
,
!
i l
QUESTION '5.06 (2.40)
Refer to Figure Two Condensate Pumps (centrifugal) are in parall'el taking a suction on the.hotwell. Each pump has a discharge checkEvalve j
and its pressure and flow are measured between the pump and'the check i valv For each situation below, complete the table provided on Figure'5.1; i I to indicate the expected change in the Flow Rate, Discharge Pressure, Land'
Pump Curren Use arrows to indicate.how the parameters should change for the running pump or pumps: Pumps 1 & 2 are running, Pump 1 shaft binds and RPM decreases by 50%.- Pump 1 is running, Pump 2 is starte \ Pumps 1 & 2 are. runnin Pump 1 shaft shears at the coupling between 1 the pump'and the moto !
R Pump 1 running, Pipe rupture occurs downstream of the check valves.: Pumps 1 & 2 running, Pump 2 check va'1ve disk,becomes: loose an'd creates-significant blockage at the check valv l QUESTION 5.07 (1.75)
The Seabrook reactor is operating at 50% power, at BOL, when-a steam dump fails open. Assume rods'are'in manual, no operator action
'is taken, and no reactor trip occur Explain HOW and WHY reactor power and Tave will chang Include any coefficient effect ..
QUESTION 5.08 (1.00) :
List two reasons for shifting from cold leg recirculation'to hot leg recirculation approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a LOCA?
(***** END OF CATEGORY 05 *****)
i ___x_
- ._ -. _
. .
. 61__PL9NI_Sy@lEDg;pEgIGN_CgNI69L_9Np_INgIBUDENI9I]g 'PAGEl 5
.
,
'.
QUESTION 6.01 (2.00)
a. What is-the purpose of maintaining 1.0 gpm pressurizer l spray (1.0)
bypass flow?~
'
b. For the following situations, list the pressurizer valve (sprays, PORVs,_ safeties) that'would open to mitigate the transien Assume all control systems are in automati . A step load reducti'on of 8% power (0. 5 ) - A step load reduction of 18% power (0.5)
l l A step load reduction of 58% power (0.5)
l -i
!
!
OUESTION 6.02 (2.50)
}
A small break LOCA causes-RCS pressure to dropLto 1800 psig causing ESF actuatio How will the following valves be affected'by this j transient.
l I
'
a. VCT outlet isolation valves (112B L'112C)
I b. CCP suction valves from the RWST (112D &-112E)
l c. CCP miniflow isolation valves (196 & 197)
d. Letdown isolation valves (149 & 150)
l e. Seal water return isolation valves (167 & 168) I
i
(***** CATEGORY 06 CONTINUCD ON.NEXT PAGE *****)
_-
6[__PL6N115YSIEUS_ DESIGN,_CQNIRQLg_@ND_INSIRUDENT811gN .PA'GE [6
'. .
!
l
. I J
"
QUESTION 6.03 (2.50)
!
Answer the following questions TRUE or FALSE
.w a. Automatic initiation of S1 is blocked when the . reactor trip breakers are open with the SI signal rese Regarding ECCS/CBS Recirc actuation, the opening logic for the sump i
,
valve requires that an "S" signal be present and that 2/4 RWST' level detectors be at l ow-l ow l evel .
c. The MSLIS is actuated by a high. negative rate.of ch'ange of steam.ll'ne pressure if Safety Injection was blocked at the P-ll setooin ." 2/4 pressurizer pressure channels above-1950 psig defeats man g .)
blocks on the SI signal (P-11 blocked). ,- .
L DelCte SO<A- (V \S l If an SI signal causes a reactor trip the SI signal may be reset 3 within 10 seconds if the reactor trip breakers are closed immediatel ,
QUESTION 6.04 (2.00)
Answer the following question concerning the Steam Dump'(SD) system a. Why does the C-7 Load Rejection Arming signal. lock-in? Why must the SD Mode Selector switch be reset after. a o
,
lar ge Load Rejection?
QUESTION 6.05 (2.00) Explain the purpose of the synchroniz4ng check . rel ays f or the (0.8)
UAT, RAT, and the EDG output breakers, In what ways do the synchronizing check relays in the RAT breaker (1.2)
closing circuit differ from those of the UAT and EDG' output breakers? Why do these differences exist?
l (***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
j
!
i
y---- - _ _ . , ,
,
,3 - 4 g, i t r:
,
j
.
.3 ..
. . ..
.
m 9
. . ,
'_$i__P_(@y[_@f@lgy@_pg@l@yt_QgylBO(t;89Q_ly@lBUGEylB1109- PAGE .7'
! +
? :*
, .;-
l]
-
o '.
. a , ,
-
'I'
,.p;
- ,+
' ' ' t,: QUESTION 6.G6 (2.10) i ' '
. The,pl' ant is'operatino.at~65% powee wi th all; contro}. systems.-in1 automatic.<
~
.
7,.
How will a LOW failure of the Power Range Channel N',t44' upper detector 3 affect following indication ( ,. i _: ." % )
.
"lt {p ,-
- + .u ' ,
..
.
' Upper Quadrant Power' Tilt Ratio.yfGPTR). 4.'
dtL
'. 's "
Delta Flux. Indication (Channal 4) h ' '
'
' e ', :y g ,
j
c.' FRV position
.OUESTION 6.07- (1.90)
l Answe;r the f ollowing . questions concerning the Eme'roency Feedwater l
'
System (EFW). );
.J
.
l What two automatic actions occur.if flow insany EFW systemEfeed";
'
( l '. 5 ) -
- reaches 450 gpm? Why is this. action necessary?
.. . .. .
. . .a How would an operator identify that' local contral had been taken ' (O.4) j of an EFW pump prior to starting i t? (2 independent methods) '[Q i, '?
.l l l g -
-j j
.
'
m,
.
.J l
l
't ~l 4 ,j; ,
{
,
p
.
t
)
'
f l
.
.f' ) k l
l l'
l l
(***** END OF CATEGORY 06'*****)
- -__-_-
y.. ,m-w
-
< ,
_ ,
q
'l
%.n..#.
ji- ' PROCEDURES - NORMAL,_ABNOBMAL,_EMERGENCV_AND
-'
. .
PAGE; . BJ !
, '
'
'8AD[OLOGICAL_CONTSOL
,
i
' &; , < .a
, Nh '
,7 l
- ' j N f.f OifQUESTION7.01'
-
(1.50) .
' the Operator Action Summary.of Et .
.
y3 , Answerjthe following concerning
'
(0. 5) ;
"J What Action, if'any, is required to be taken!if a Phase ,
"B"
- j
,
,
" Containment Isolation signal is present?.
,b ( 1. 0) >
" Wh aff; two parameters.should-be monitored following SI-termination: :
to determine if SI reinitiation is:necessary? .!
! /i
-
d
'
'
)$ ' '
j ' OVESTION ~7.02 (2.50)
I' Indicate for each of the f ollowing separate and independent situations :l whether the plant should REMAIN AT POWER,. REDUCE POWER, SHUTDOWN.or be TRIPPED, Assume no reactor trip occurs and the plant is initially at l 100% powe !
I I An urgent alarm is recieved on the DRPI panel falar !
t
'! One control rod in a shutdown bank drops into the cor I The Daily Leak Rate Surveillance has just' been completed and l
, '
'
indicates an increase in Reactor Coolant leakage tts 7.0 gpm l
,
identified leakage and 2.0'gpm unidentified.
! Flow is lost in both trains of the Component. Cooling System and d
,
L >
.
cannot be i mmedi atel y restored. - No high temperature alarms are I l
< recieved for the first'12 minute l s. It is established that. a loss of containment integrity '
has-l existed f or the previous 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ,
I d
!
i
,
<
l QUESTION 7.03 (2.00) ,
~
l
'
a i
'
Answer the following questions regarding procedure 0S'.1000.01,'Heatu ]
l from Cold Shutdown to Hot Standb a o What is the required status of the reactor trip breakers (open, ( 1. 4 ):. ;
l closed) and the control rods (SD banks in/out,' control banks-L in/out) duri ng' ini ti al criticality heatup?. 4
l l What is the minimum number of SR NIs that must be in operation in (0.6) ;
. Mode 3 reactor trip breakers shut?
l l
l (***** CATEGORY 07 CONTINUED ON NEXT.PAGE *****) 1
! '
, ,1 J
O, s
.
_s sj7
- . . . . _
_. . 7 A ;.7; a.gic -
, 1 PROCEDURES - NO'RMAL (-ABNORMAL dEMERGENC LAND
,PAGE' 59
^*
6021969GIC06_C9tfIS06" g -4
. <
$
'
~GUESTION 7.04 (2.50) The plant is in mode RC5 temperature is lOS F.and,/the' pressurizer is '
vented to atmosphere via a small.' vent valve (RC-V468);J/'While conducting:
-
g,. routine survel11ance, the CRO in' advertently re36ts tr ain "A" Low Steam-
- 'line Pressure SI-instead of trai n, " A" Feedwater Isolatiore. EXPLAIN the
'
>pyant response for the transient. > usume ithe .f ollowing equipment statusi a '
A'CCP i s in Pull-To-Lock 6 f CCP is off 'S$ N A RHR pump is operating B RPR. pump' i s . i n Pul 1 -T o-Lati -
i A PORV'is inoperable / 6 / j'
y/
(
All other equipment is in a Normal Mode 5 linerp5
, .
( / '
/ { { / '
/ s ,/ i ; , ,
,,
'
l QUESTION 7. 0y (2.50)
/ ,
room l The plant is oyeratingThe at reactor 85% power and turbine and'the'
a. fire occurs are jnjthe control subsequentl tripped, l ventilation s/r%e )
1 All RCPs are stopped, MSIVs and their bypass. valves?are closed, and the l "A" Remote Safe Shutdown panel is manned.
l l l What system (s) will be used to control the fM lowing parameters l while cooling down to 450'F and 1000 psig? ,
i I
'
!
l 1. Main Steam pressure 2. Steam generator level 3. P.essurizer pressure 4. Pressurizer level How will the plant be depressurized to 1000 psig?.
y> -
.
} j
'
,
/ f a I
QUESTION 7.06 (2.50) y<
) \ Step 2 in procedure E-3, Steam Generator Tube Rupture," states!' (1.8) ,
- " "Identiqy the ruptured SG(s)." List three indications the' ]
that should be used to identify the ruptured SG(s). -
l
6 > t
' What action may , b'e requir ed if offsite power is 1ost after S1 is '(0.7)
- reset? j v
i ' / s'
i a ;
, .
3
, ;
.i
( * * * * * ' C ATEGORW 07 CONT INUED ON NEXT PAGE * * * * * ) -
s ,
- li
'
/~ Y ., ,- ~ r d
, ,
+ ,
IV Y
'.
_
N- _ _
-
'
' PROCEDURES - NORMAL1_ABNgRMAL 3_EMERGENgY_ANQ- PAGEc 10
. " '
.BBQJQLQGICOL_CgNIBQL
.d
.
-j
, QUESTION 7 . 0'7 -(1.50) L When' critical and immediate action is required f or work of short duratio '
Health Physics supervisory personnel'~r o the shi'ft superintendent-may authorize entry into,an RCA without an:RWP if three conditions-are me LIST'these three condition r
- 1
l .
! 'l
'
l
-)
~.1 l
i l \
'
l l
l , 1
< i
. .
!
l
. l (***** END OF-CATEGORY 07 *****)
'
. .-_ a
, ,
_ _ _ _ ,
@ __@pg]NJ@]B911yg_PB99EQUgg@1_ggNp]JJgNS 3 ;,@Np,,g]D@ljpNp PAGE 11 l .
'
i
*
l l
~ QUESTION 8.01 ~(2.40)
! L Classify each of the following occurrences using.the Event Classification sheets and the CSF's status trees provide Identify what factor was used to determine the classification, A transient occurs which causes a PORV and its block valve to fail- ! in the open positio A reactor trip and S1 subsequently occurs due l low pressur The containment purge that was in progress cannot be-isolated and containment post accident = monitor levels are 12 R/hr.
I One diesel generator is inoperable and a loss of offsite power occurs. The operable diesel generator fails.to start. The' load i dispatcher reports'that a lighting strike disabled the switchyard
~
l and power cannot be restored for at.least one hour.
l .
.
L An accident in the containment results in an injury to a worker.
! The worker is in-contaminated anti-C clothing and has broken his I le Due to the accident the worker receives 2 Rem of radiatio Previously he had accumulated 500 mrem for the quarter and year.
l l Following operations at 100% power'for six months, a main steam L l line rupture occurs inside containment. Due to Containment Building l Spray system malfunctions cntmt pressure reaches 22 psig. -Only one EDG started on an ESF signal and the load dispatcher predicts a loss of offsite within 15 mi nutes.
i QUESTION 8.02 (1.50)
*
Under what conditions may work be started'without a work request and-whose authorization, is required? QUESTION 8.03 (1.60)
*
Answer the following questions concerning Fuel Handling and Refueling Operation . What is the minimum- allowable boron concentration during core (0.5) alterations? Why must 100 hours elapse bef ore core alterations are allowed? (0.5i
! What action, if any, must be'taken if the audible indication of- (0. 6)- l the c ontr ol room SR NI is lost during core alterations?
A l
i (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
]
a _ - _ _ _ _ _ _ - - _ - _
v _ __ _ _ _ . PAGE 12
.
LO[__eQdlNISIQellyE_P69CEDURES_CQNDlligNSt_@ND;Lldll@llgNS-t
,. i
:.
QUESTION 8.04 (2.50)
a. Two separate.and independent 1 diesel generators'are~ required to be 1 operable in mode 1.. List three auxillary components that'must.be operable to support this requiremen b. Describe the special check of an EDG thatLis required prior to running it for surveill ance between November and Marc ! i i QUESTION 8.05 -(1.50) ]
Answer the following questi'ons concerning Operations Group Controlled - j j
. i, Key a. Once shift turnover is complete, i s i t' permissi bl ei to' .l eave . the key
-
H j cabinet open for easy access during the shift? Why or why not?
'l
.. .. i If a lock in-the plant is compromised, what must' be done i f.futureL j plant conditions will not allow access to the lock? !
QUESTION 8.06 (1.50) a. List two of the four parameters / conditions (besides' baron (0.8) concentration) that are used to determine if the cold' leg 1 accumulates are operabl ! t (0. 7 ) ' b. Accumulator boron concentration is-less than theLTS: minimum . Is the USS and the TS surveillance sample is due next shif on the following shift required to perform this TS sample? Briefly explain why or why not? j
'l
'I i
-: ]
i
!
't (***** CATEGORY 08 CONTINUED ON.NEXT PAGE *****)
'i j
b _ - . _ _ _ . . _ _ . _ . _ .
,
' 9$ _ _0pMJ NJ $JB8]]yE_ PBgCEpUBE@2_ CgNpj IJ 9Ng1_8Np_6] MJ J@l J gNS ,PAGE 13=
.
,
. . .
.I I
.
k
QUESTION 8.07 (2.00) Answer the following questions concerning facility staffin Assume i plant power is 100% unless otherwise specifie i Choose the minimum number'of Radiological Control s technici an (s) . that are necessary to relieve the offgoing shift for present : plant conditions in accordance with T ; A. O q B. 1 C. 2 D. 3 i Choose tne minimum number of fire brigade members required on shift'. ' A. 4 : B. S C. 6 : D. 7 Choose the minimum number of licensed operators required on shift -l for safe shutdown.
l A. O l B. 1 l C. 2 D. 3 .k l ' ' Per Tech Specs, choose the one set of crew manningLthat best represent j l l the MINIMUM requirement for reactor startup after a: reactor trip.
i Select the best answe ] l A. 2 SROs, 1 RO in the control room, 2 AO l B. 2 SROs, 2 ROs in the control room, 2 AOs C. 1 SRO, 2 ROs in the control room, 3 AOs , 1 D. 1 SRO, 1 RO in the control room, 3 AOs l l l l QUESTION 8.08 (2.00) L In some situations deviations f rom procedures are permissible without l requiring a change to the procedure provided certain provisions are- i satisfie For each of the following devi at i on s , list the provisions ) that will allow their implementation without a procedure chang Procedure steps are performed out of sequence.
l Non-applicable steps are omitte <
(***** END OF CATEGORY OB *****) (************* END OF EXAMINATION ***************)
_ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ -
.
,
-
-
q
, y
,
)
l . .. P '
'
Equations - l
'
p= 0 Q = MAh + '!
- tK eff 1 + kt *
I
.; ..
Q = m,c AT 26 p i p SUR = !
.. 'A* + (6 p) I Q = UAAt C3 (1-K3 ) = C2 (1-K2 ) i -
h( = K 2 p = po 10 sur (t) l 1= 3.14 -P = Po et /t j 1 Ii e = 2.7 ' S ' SUR = 26 06 CR = '!.s
:
,
t 1-K l
eff i
'
l '
g= - 1* + !. 2 ,_ p 1 _ CR y j p p1 p-S M CR g i
. . . "
y = h-hf _ 0.693 -
'
. seconds A* = 10 h
fg t y = s-sf i
\
s I fg l l \ Conversions
1 curie = 3.7 x 10" dps 1 kg = 2.2 lbs
t 1 gal = 3.78 liters 1 gm/cm3 = 62.4 lbs/ft8 I 1 ft8 = 7.48 gal
'
1 in = 2.54 cerri ,, .
. *
.~ . 1
',
z .a z f . :. ' g ;,W,, " ;. 1 yr = 2.15 x 10' sec: '. '. : a 'l gal - 8.3453 lbe
,
'
l , 'l MW = 3.41 x 108 BTU /H in Hg = 1.037 p':. , 0 41; ps:(
*
+ '
.
..
.
3 ,
,
;
-
,,
*
. . . . .
.
. ,
- * .,
. .
, ,. .
.,..
.
, .. g; .
a
.../ .
.
.
.;
,
.. . l
* '% [* , . , f,*, .Q. A-'t,-
,,, fs
."*
*
.
,
I
", e-
*
,
. ='
' '
..
' *
. * *
* *'- .. ;-.
,, ,, ,
,
. _
_ _ _ _ . . - - - - _ - . . - _ _ _ _ _ . _
,
'4 %
!
.
A+wed- p r-9 ( n . f,p e r ,, - Ryfure-
.
h
.
? r
~
N
"
r ! - a i l l sWM h t<,, mf _
#f ,
en P< e Ca</d P/w L~d i a-h 1 ) c.
i l a' e
" /ncreasa Dec.<mse = Wo Ohwje-i - ,
ftjW) 5- C-w___ . - _ _ _ _ _ _ _____ -- ___ _ - _ _ _ _ _ _ _ = -
ca on si r os oit E .Ce s _ 7. JOffr o 0rs 3rs osIAm_ a c Ib s
.. .-
L
; O .
I J CoN.ff gSe t f dr no u.. G f 5e (ed o . s 0s 2 .w M2 o Tt 4
'
ff d c 'e-
.
Wff Jes f e e s s A 5e
%ct n.w_
: 3 e t
,
l * e nt lE iweorhE ceu MC_ T, Ee ree" Er o -
.
g 1 R A _ s=ea =t E o , n e d uor- d uvr s= n dt e n - wo c '" t uori n = r
:C o E
N o ,
- c c reO.Po _7e B.re* rpo e
7o B.pc" D.pom 5Cf_ _ G c tO HG " ' e l L IG e '
"I I s o~
fGl L
.
l E
.
l f l 6l {.
,_ _ -
_
\ .
. ; . -
Y - n: . : . l 3I l l l
^ . l ols e D N bes t! e a!t m E s= u o n
e G te oft e f w&n f r e tu s-i f nec r oC sa i t e p n E e .s ru
.
s 115 hew r-c M te s81 ee a e E G to1 1 n 6wo c b y- 3 Emoite Ae Eop s f A slh ul t o%cE 0re o D e 4ff es Net e M s g,n E J eog T R c f dos n er oe Abn A 5e e a so S tf - t , R e g e g Ernt eeu l t ub r um Eno of c ,,o s A
.
E n n s w n n en d e e - d a, d a uori iC o uan dn, ,, g H T I r o e r , e r r o B. p o m SOf
.
. Bce C S sc H p Z Z 6
. r G G o
l
. gs e
.
- .
W - O g< l l
.
l' L l o e _ F grh ot e te t a s 8ar r N
_ r n t1 n e _ O T
. _
i_ .
.
.
,lr'J e
ot ff
- o oe ef riv oC
&. f o
e
$et nn a aeeg g eh e
n _
-. e d .
e e dt O e n ro o1 wB! r c e ru n rn g o e et n.. _ F. :
", =r e
t1 G o - eis E w> s co ^ote; ae W T R :.
.
_
. -
0t 2r i
[ : o cs s. !
o i A
!
Ss g c r;r e c F E m_
.
L e- cs . Cltts e i e.tlsgr_c
- rT wh - !
L - e- e . naess e o g i 5 A__ . ,
=e t ">t, : e Ldc ttubu 3 tf of e od i gof 5 _
g n
- lol o sn r r eu e Eno suonn mk c A
o
,e u sh o :C iree repe L
r c u.s _ o - lei y o s cet s s 5D
.
Bco Pl pe9'
.
C c
-
c ( P IZLt C d . 6 Egu l7l e l _ ~
\
.
Y C N E o G T N 3 F r R E
H- d . E V R e ec r e e rl M E F es ee t Gwr Eope Ss E L p e Eopie d A c o Oe U E n O+tas NL Nbeh S ( S tf 5 tt U of E e N o
.
o w . o
=
Eno nm l I lo on aan ono vor U l e
]
e l e E cf s y g s B. c e . a b c H P Z C E _ S _ _ N _ . O Y I C _ _ _ T . . _ C N _ _ N E _ U g G _ _ F t a R _ _ r E _ Y e g MS E N _ . _ t _ T n O . e
.,
_ E g . . i . _ F t t t ST I r s i _ A y n UI l _ _ . S o. o l o *es e e m OD F ee t c $ t n r a EN l L s
-
e t I e NO a A su o o S t n AC ic C o L r C sc N t f C t I L c e T sc H P Z E l _ I C R . _ S 6
. C I !t W
:} e mio s le pe
~ rs o e t eo s i st e.lr ~ a td rn d f!ac ocl ue fr d; e edetna vrL r ee ' u t e n t t st n nA
.o ur sre: s ee ds rot e *o s: E a sct eje/t
- t s g n. h oeu arde rus d e g-r une t - ct L. r o r. e oact o -
'e
d d 6 d 1 1
1
-
du * d o d e r e n h n h r o f o e
:
c dl a t d l 1 li e eeht nb
.
ep nt - b en g e c t s ui - L in eta r e' ip ou d o n esf w ! ee t s ovt t d o . t rh dlt yn E
-
t rm p se e l a re ns oont dot o' e Av sfL r e e er h / reie e( e i y h hg e/R r r p vs ct nqu tt us s . cf Ed A Rm ano loa e ca r e oe n n ol n Dio t re e eh oe e os na r p ol go hht icsd A Nwr p hw+8 yE2 15 tte i oel t o co ne t s=pn ou ri eh e ee( e s m r5 ,d r t u eC t i t oi pwrun 3o At i n a22 getecf a e ola nc m s t s d o Rur oe o eda sc e - V su nee m reed r e fe r in5 t w1 eeni - f s e utt o ee eh mre dt sf e te odn dy eo dce tf oict o n t udan r ert e me brr r=o csd so ee cth ojoct v srn e e, sc out :ojno soo o! l ess l oe rf ao vhs or reurp euo oo or e!r t ns Lat oo E. s = H. p a f 5dd M.flpa r L. S F. s
.
d s c o b .o f
2 1 a 5
6
7
0
)s l
.
(
r o t l s .
.
e aonr hci nte m p
.
s t gn s a g n h c
.
rdzo nl one e a c go g r t s=y r 9
n g
-
f o Ls c me ef n. t y a stti e > t d + ev n 'L d t c s e .d i
/
lsleed e . nd oodio ar ti t e em cl oA C en r nvi k r e dot iE u o nrc ec t' I red t a3 et e r e e f e f t a p h e sao 1 o. o
-
e/ t tst ac r0 dn C dc ia c n e l eys r ns ewi ndi e es I e tb t r e a lo 'm eeis1 c o ss r n n2 c h w1 opnlder f ed i G . tn
l ld i ed rt o b.le o A y'g
'
d- fenp
! -
oei eo a m2 a- o oet ou t s . y e yL r dsa n gr eC l c t a de b e rc ah.e'nf a to ti enior o nl s l
.
w Lat!e eth w b a2o t nf if ldo t( S, C ee o t et
). ed eis o -
.
t le i r ot rt eoe l ec t n do r o ta r af a ral st nt et c o- o cl ssa ae s psj dca r e Cmats o br fii orr ef hss tete t c t c> sbo epa s o njmt e t ee 31 S Aprnet t oh s ss nt e ra gnt lale ulo as a e rfe a tihp nie t a srut ob e
- ,
t a e i o e t.ny :o 1 Y e ce Sd S. c m i b F. r F. I F. * A. w c H. p e o b s c a 0 b b a b 2 2 3 5 S C 7 8
% 1 3 1 1 I I 1 1 l
e d t-g l o n cd % t
.
io to n
.
e ec t c r i t . f4 e d h n . t ct e e en . nd e e n
=
f l e i s e t e o e
:
e t i. e o t rt nn eo t d g o j nl ie yrm lT mm eHpe sWI ip
-
-
r e 'e L': mp
. *evp eu e
t m r e n coseu uq i d o nso l ovl A - d u ec bh/ o t m n c e o nE rS r q e a o fn dowso t C o r eete c0
) l o dt nFi eRm a t c e nt e nl
_e b ec o s e e oc eco l e
.
D n6 d n e1 t o s t r u hts e h2 s t ra du e nod e c n ds t e n ! s-sP e.a e n sip w- orr tc mrt i eh e( o l l on ds ru o e iO r r y f nl rE t _do i Se ! eC e( l e a tS cd m co oo e e2 ei ptude t e 8llo el pe gt ee r e ! At l o ) lt i i r ec o1 a c dfo oo o _m Vs fe ut l a ce c c d n te tr o r nty i r t t y En l r eF S n onna uo pent odl s ea rt e t n e fs e f nn e rT r hee st i e d t r op f f iwh e _tmce r o m r u3 oot olo sv o u t nod ac br tte oU p tot nttr i e repm oo dctn ren s o eec r u TLN AO NP E n o r sola lMt sO oe e e s st en s s= ec t s u rh3 et es ao oH n oT eIl a a r oon ojet zote arot vr r e e 1
:
e EyR t FR
:
st Sd M L. c L. r L. m lc !. R.W p F. m n o H. p p o f p tU 0 d e s e o
-
e o EtC LE E 9 % le
' 9 D I 1 G 9 % a PGC 1 T 1 I 1 1
--
MRO
!
Wr P E y g
-
-
tn e I s - e b o n o' d d d p s e od n ot r et e t s t cne a Mna eua r r C o s s n a i et t a - jp V c e r Su o nl ap t
,c C TN g m ler p d i Tno r o c u
Mg a L n i u u e c ri e e n dS t e EEV P E Ac tc ot r sS et r i nl t o s C
==
o n cn eo i r c g ec j e m y n r a se sw E w l ot ee c w1 rd a ee c le o o . ED tE ela e s n m f i o l t i ioru o rf T eL t T Tst e R g M lay l Parn et o tan f t ye RS o o-i d R I f t i n.ci d n emfelt rta o a Ne a ct r t OL F fl ta, a l ni le o oeb of 8
. H ro ono e
.dt re ennt geai e n s se di oS ac e r. ot o
o or oe t c hp ue % g, l e ntir ml oof r e t n o e egep e rt sp en meere s t s ece i g
'v c. o o i L
L
*
L. C S SS
.
H. a
8
A. o
t. C 5 G D. H O
f. C F e JC 8 .5
~
I 1 1 : 1 91 2 1 1 1 1
-
-
E
'
,
~
=
. Symptom / Title:- Peacedura No.:
Revision No./Date:
, SUBCRITICALITY F- ,
01 / 07/23/86 r
! (RED) Go To FR (ORANGE)
r---@ R
"O NEUTRONFLUX # INTERMEDIATE NO ENTER'% LESs THAN 5% - (RTM YES ~
RANGE SUR - ZERO*0R NEGATIVE vas (YELyj Go TO
, FR e ,
INTERMEDIATE RANGE SUR go ) i
-
MORE NEGATIVE ves INTERMEDIATE
"O AN 0 2 DN lj ll RANGE - = LESS - l THAN v CSF ,
14E3% SAT-(GREEN) . NT)' e GOTO FR o l INTERME01 ATE No RANGE SUR ZER0'OR ves NEGATIVE : NOTE: USE GAMMA METRICS -
':
CSF \
' (GREEN)
-
SAT
.
I i i
,
.
NHY MISC:RE060004.DGNil Procedure N ! Symptom /T ties - Reviston No./Dete:
..
'!
CORE COOLING F- . 01/.05/14/87
(RED) ' GO To rR- (RED)
CORE EXIT 2 fuLRANGE ENTER h $*LES5 m }g
-
TEj- YES
:
_
.
,
(ORANGE) - 4a oo To FR- CORE EXIT NO TCs LESS _j Tm WF YES pe FR (ORANGE) *
RvLIS N0 i I AT LEAST NO FULL RANGE
"'""
OPE RCP GREATER RLNNING ygg THM 40% TES l
,
I (YELLOW) # oo 7o RCS NO 9 FR- i SUSC00 LING i
{
IE$ YfF YES ee l _
(ORANGE) '
%
_ l NO i MIC HEAD GREATER YES THM x a4RCPs
,44% e ggz. . e na (YELLOW) !
.
.( ogen) . CS,
.
. _ . . . . . . .
w ggggment C0wui usiiwi . ControlKumber- l
_ __
, .5ymptom/ Titl . Proceduro No.
i * ' Sg Rsvicion No./Date: HEAT SINK'
'
-
.
.. 00 05/16/86'
i
.
- RH1 TOTAL FEE 0 WATER No '
" FLOW TO ~
SGs GREATER YEs TyN- (YELLOW):
. . . . . . . . . . @ FR G o To -
= PRESSURE IN No ALL SGs ' No ENTERh SpVEL L
- E hH N 125 YES p , YES d d :(YELLOW) Go To -
.,........ FR NARROW RANGE sc LEVELIN ALL _
SGs LESS THAN *E3 86 % NoNAovensE ADVERSE (YELLOW) u tasi- AT -E * To SGs GREATER SG GREATER ...... THAN 65% WR THAN 25% NR FR PRESSURE IN ye ALL SGs d ' ' ' ~ LESS 1185 PSIG YE5 (YELL.ON) GoTo
$***** FR NNE NARROW RANGE LEVEL
*
SUILDING NO IN ALL SGs PRESSURE GREATE R . <Es GREATER THAN 25% THAN ygg . i 4 psia CSF
. I -
'
(GREEN) SAT
.
l
, , ,
_ _ - _ _ _ _ - _ - _ _ - _ _ - _ _ _ - _ - _ _ _ _ .
. Symptoa/Ti' clot .Proccduro N * ~ a, Rsvision No./Dsta:
INTEGRITY F- ' ' 00 / 05/16/86 I
=
m (ATTACHMENT A)
J v E
% ~
$
N Ti T2
. COLD LEG TEMPERATURE R ^'t acs (ORANGE)
'""'~ GO TO
-
${0 tEG
,E.. ERA, RE -
"
[""""
.
FR PolNTS TO YES RIGHT OF ALL RCS uuir A t0Lo LEG NO (YELLOW).. GO TO T TEMPERATURES _ e
*
FR GREATER THAN VES 250 F (T, ) L., gg3
.. TEMPERATURE C OLO LEG NO DECREASE IN ALL COLO yo L fiM PE R-
;ruRES
-
-
ENTER h LEGS LESS THAN 100'F YEs GREATER THAN 280 F (T 2) ~ t IN THE LAST 60
"'"""' CSF (GREEN)
SAT (ORANGE)g GO TO FR ALL RCS COLD LEG NC ( ATTACH M E NT B)c- TEMPERATURES - GREATER THAN <Es RCS PRESSURE LESS THAN NO 250 F (T )
' ~~~~
GO TO' F IRES $URE vEs (YELLOW)
$e FR euit No Rc5 " "
cIE$EYr'Hd urr'
] (GREEN)
, CSF SAT (GREEM)
Ii , CSF SAT
* ARMING BISTABLE SETPO!NT
.-
' .Sympton/Titic: Prrecdura N R visien No./Dato: . '
-
i INTEGRITY F- '
' ,
00 / 05/16/86 ; l b- __
.
i l
,
*
i 6 e . e i e . . i j
. i ; . ; .
t i i ,
. ., , t e e 4 i i , . . . l
. . , e i * .
.
. . i ( i
.
i 3 i t i 6 i . .
* i i . * . emana. * .n.m ma . ,
LW%# LuiFV . t
.e-==== esamamm - es-==
s , } * s s / *
. . , , i /
6 . / e
'
.
i
/
. . . . i i , i . / .
, j . . . , , , . . . ee i i i ! , , , . .
..i e . . . t e , s i 6 i . . . . . . i i , ques-. /* , i i e i '
. . i . .
, , , i e i . e %= : i. s / . . i e i . ! i 6
.
i . 4 s ema re a r. A ./ s I 6 6 6 i e a i 6 . . . i6 ' i e i i i e 8 e i i . i
. .6 e i s.v w v ir wiw I
, , . i i I'
i , . . . i 8 6 * . 1
. a i i L t .
i e I i i J , 6 i .
. 6 . . . . a 6 . . i .
J . i e i e } . . fi i _a i i , . i 'l' i e . . 3 . . i
. ,
, i e i . . . i i . . i 4 . . . '. i6 i 6 . . . .
i i 6 , . . . i e . i . . i , e i e i i i p i e i i i i i-i r ! . . . i i . , i . , .. . . . .
"" i e i i 1 e i e i .
a
. i . t i e i e i . . .j . i 6 e i , i i . .
1 i e . + I e l i , . . . i i , i . 6 i I
' ' ' ' ' ' '
'
.1500 ; i .l: . . . .
, . i , i t i
, , , , . . , . , ,,,. . , , , .
_ . , , , , . . . . . . i i i . . gg ,
, , , i i . i , , ,
, . . . . . . i e i . . ,
, i . i e i e 6 i i . . , i .l .
e
. . , f f , e
. * i e is s
! I i e 6 i (f l .
*# i . . , -(. . ,
t
, .
. . .
e i e i ' ' LulOOC . . ', . . . . , , 3 , , , . , . .
,
.
e y i i I
,
i
= , . ..
. ,En= l i .
,
i
. i e
i . . wp . . .
,
~ 14 %. f f o
O o _. : - . V F _
.
,
.
g i
'
f _I 4 e i . l' ._; : n. 500- m,, ,, m m m , ~ I V RM 41V6 w
>=-
. - - - , , ,
V nG.Ll1 I . BG L/ <
)
'
. i J
. ' I i !
.
t I - I f# 1 i r
/ I i
j1 I * i O s i i s 400 10 0 / 200 I I I 300 19 4* I I ' Ti T2 TEMPERATURE (*F)
.
M A P *
. ! , '
NHY MISC:RE060003.DGNil
' '
Proceduco-N Symptom / Title: Revision No./ Dater
..
CONTAINMENT 0- . 7f5/14/87 (RED) ca 70 FR- CONTAINMENT NO PRESSURE (ORANGE) ENTER h LESS THAN S2 PSIG YES
,,,,,,,,,,,,,,,,,, GO TO
, FR_ s I !
CONTAINMENT NO PRESSURE LESS THAN-(ORANGE)
,,,,,,,,,,, GO TO 18 PSIG YES . FR- m I : .
CONT AINMENT- NO BUILDING LEVEL LESS (YELLOW) ca 70' THAN 5 FEET YES 49 FR- O l 8 CONTAINMENT NO POST ACCIDENT MONITOR LESS THAN 10 Rem /He 'YES _ M CSF SAT
-~
,. ,. .',. ',' O.f{ ,h
{a, ., .
.
_
:.-uumbu sua u a
. , [' Symptom / Title: 'Procodurc N R: vision No./Date:l .. INVENTORY F- / 05/16/86- .
i (YELLOW)- Go To-
-$** F R l. 3 e
RvLIS FULL wo RANGE LEVEL _ GREATER THAN
,
981 e
',, .GO To (YELLOW) FRl.t
. PRESSURIZER No . (YELLOW) GoTo i tsyst ************ '
.FR ENTER M LESS THAN n% vt5 e
e e o PRESSURtIER No
'"'
anpITea -
" (YELLOW) GoTo THAN,% **
FR J L RVLIS FULL ge RANGE LEVEL NONA0 VERSE ADVERE - GREATER THAN SETPOINT SE TPOINT - ggt VES LT % M%
.
h-4 ' CSF murAme SAT-Sult.DNS NO (GREEN) PRESSURE _ GREATER THAN TII
.
__ _ _ _ _ - -
'
* * _ . . -
'PAGE~ 1 . .. . . ~
.
,
'S __lHEOSY_OE_dUCL@@B_ggWE8,,EL@d[;OEg6811QUt_
t FLUIDSt_AND IUESUOQYN@dlCS
..
-87/07/28-BARBER, .
ANSWERS -- SEABROOK 1
,
\. I ANSWE .01' (2.00) I t becomes l ess posi ti ve -(0.25')
^ Increasing temperature forces more baratedtwater out cf-the core. This reduces thermal absorption and adds positive reactivity.toLthe cor (0.5) F (0.25)
The change in density.at higher temperature is' much greater ' than at : lower temperature. So mere boron atoms' enter or leave the core at higher-temperatures which causes a larcer reactivity change for'a given temper - ' ature change. (0.5) Lowering bor on concentration over J11'f e makes -MTC more ' negative. EO.53 (causes its contribution to power def ect to' increase) REFERENCE WEC-Core Control for Large PWR, pg 3-14 ,3-20 Seaerook 85-4 Oper Char LP EO 2,3 , 001/009 K5.15 3.4/ OO1000K315 ...(KA*S) I L ANSWER 5.02 (2.00) l Same for both EO.53 (Rod height is dependent.uponEthe, amount of reactivity needed for criticality) Shorter for startup #1 LO.53 (The reactivity addition rate is~ greater thus a shorter time)
- Lower for startup #1 LO.53 (The higher rod' speed _do'not allow. time for I neutron population to' buildup) Higher for startup #1 00.53 (This is because of-the-higher reactivity addition rates)
REFERENCE WEC-Core Control'for Large PWRs, pos 8-12 to B-54 Seabrocu 86-1 Subtrit Mult LP EO 1,2,3.6,7,8 001/010 KS.OB 2.9/ ...
~_-_-_a_____
. , . . -- .
, _
,
. , O
=St_,10EgBY,,gE[UyC(E@ Big 0gEg_E(@yl_gEgg@llgyt;E(ylD@t_@ND, ,PAGE 15 ' U
'
' :IUEgdgDYNQUICSJ ]
.
ANSWERS -- SEABROOK 1 -87/07/28-BARBER, '
,
J OO1010K508 ...(KA'S)
.
-
i ANSWER- 5.03' (1.60) 'l
, DNBR decreases ,
'
q DNBR decreases , ! l DNBR increases ; DNBR decreases 4 items CO.43 e j I REFERENCE ,
-
,
j
.
WEC-Therm. Hyd. Principles and Applic. to the PWR II,-pgf13-23,13-24 i Seabrook 86-l' Power Dist Effects on HT: EO.1,3,4-
'
j Comp- . pg A-18-
. .
No. 7- 3.2/ .
)y
:I I i L C E ANSWER 5.04 (2.00) -
' 1 j
~
~ After.the power reduction, the higher. equilibrium Iodine concentration in the core bottom half decays to Xenon.l[0.53 This causes a larger j proportion of Xenon in the~ core bottom to shift flux to the. top..CO.53 Case 1 would be a,more noticeable Xe transient EO.23'because,the power change occurred rapidly with respect.toLXenon's abilityf to maintain equilibrium. CO.83 REFERENCE WEC-Core control for Large PWR's, og'4-24 to 4-39:
Exam Bank 4TROO2 , HO-TAA-8.15 Seabrook 85-5 Core Char. LP EO 1,2 001/010 K5.34 3.2/ OO1010K534 ...(KA'S) l
'
i _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _
PI -. THEORY OF NUCLEAR POWER PLANT OPERATION,_FLUIDSg_AND PAGE 16 ,
' I ^
IHE0dODYN9MICS
.
ANSWERS -- SEABROOK 1 -87/07/28-BARBER, , i l ANSWER 5.05 (2.25)
"
"
sphere of influence of DRW decreases. 00.25] As Tava decreases , control rods decreases due to increase in moderator density. [0.50] DRW increases. [0.25] As boron conc, decreases, more neutrons can reach the control rods . [O.50] DRW decreases. [0.25] As rods are withdrawn from the core, they see less flux; as rod worth is proportional to flux, rod worth decreases as rods are withdrawn into a lower flux region. CO.50]
REFERENCE WEC-Fund. of Nuc. Rx. Physics, pg 6-27 to 6-32 Seabrook 86-1 Reac. Bal. LP EO 2,3 001/010 K5.04 2.2/ OO1010K504 ...(KA'S) ANSWER 5.06 (2.40) EO.10 each]
:: Pump 1 ! Pump 2 Situation !! Flow l Pressure Current il Flow l Pressure ! Current
__________;;______;__________;_________;;______;__________;________
^
a ll v i v l
^
ll
^
v ! __________;;-_____;__________;_________;;______;__________;________ b : v l
^
l v l1XXXXXXiXXXXXXXXXX;XXXXXXXX __________;;______;__________;_________;;______;__________;________
^ ; ^
c lt v i v i v ;; l v __________;;______;__________;_________;;______;__________;________ d ll
^
i v l
^
llXXXXXXlXXXXXXXXXXlXXXXXXXX __________;;______;__________;_________;;______;__________;________
^
e !!
^
l v l
^ : v l l v
_____-_ -__-_______________________________________________________ v = Decrease ^ = f r,cr ease > = No Change REFERENCE WEC-Thermal Hydraulic Principles, Vol 11 Ch 10, pg 32-48 Seabrook 86-4 LER LP EO 2 KLA Appendix A-Components: Pumps-Centrifugal M7 -- ____
<
,
;'1
/ ' 5. - THEORY.0F NUCLEAR POWER PLANT OPERATION 2 , FLUIDS3 _9Np PAGE 17'
'
" '
ISERdppYN9dICS ANSWERS -- SEABROOK 1 '-87/07/28-BARBER,' y ANSWER 5.07 '(l . 75) Tave decreases since heat removal'is in' creased .
[0.53 i Rx Power increases due to the positive reactivity added through MTC. '[0.53 ' l Doppler would add negative reactivity'due to the power-increas ;[0.253 -]
Power stabilizes at a higherfvalu [0.253. 1 Tave stabilizes at al lower valu ~
'EO.253 1{
.
l
.
d REFERENCE WEC-Th. Hyd. Prin. for PWR II, pg 12-40 to 12-45 j Seabrook 85-4 Oper-Char EO 8 l 041/020 A2.02 3.6/ y 041020A202 ...(KA*S) j l
'l ANSWER 5.08 (1.00)
Remove boric acid that is precipitated on upper-core. surfaces [0.53 and.to" i terminate any boiling or steam formation in upper; head region CO.53l {
,
REFERENC Seabrook ES-1.4, Transfer to Cold Leg.Recirc Seabrook 86-2 ECCS LP EO 1,2 i 000/011 EK3.13 3.8/ OOOO11K313 ...(KA'S) ! !~ ! l-1' i
<
_ _ . _ _ _ . _ _ _ _ _ _ . . _ _ . _ _ . . - - . _ . _ _ . . _ . _ . _ _ . . _ _ _ _ _ . _
a 6 ( _ _P LGNI _ S ySlE 05 .i D E S IG N ,. _C O NIBOLt_8ND_INSIBydENIBIJON LPAGE 18 ,,
-87 /07 /28-B ARBER, i.S.
- ANSWERS --'SEABROOK:1 . _; ANSWER 5.01 (2.00) Prevent. thermal shock to1the spray valve nozzle ~and associated' [0.53 '
: pipin EO.53 . Sprays- CO.53 2. Sprays, PORVs .
- EO.53 Sprays,'PORVs (Reactor will: trip on high pressure)-
Deduct ( . 2)- for each. additional incorrect respons REFERENCE Seabrook PR-6 Seabrook 85-3 Mit.JCore Damage LP EO 1 010/000 K4.03 3.8/ K403 ...(KA'S)
,
ANSWER 6.02 (2.50) shut open shut (0.33 if sufficient flow exists CO.23 OR.vice vvrsa shut shut 5 items CO.53 ea REFERENCE Seabroo CS-28, CS-30, 15-22 Seabrook 85-2 ESF LP EO 1 013/000 K1.11 3.3/ OOOK111 ...(KA'S)
-
_ _ _ - _ . _ _ . b .___.___.__._sm._._-_ _ _ . PAGE' 19:
, " , a6[__PL@N1_gl@lEdS_DE@l@N_ggNIRgL(_6NQilNSI69dENI@IlgN t . ANSWERS'-- SEABROOK 1 -87/07/28-BARBER . .
ANSWER 6.03 (2.50) a.'True b. True , c";. ;W - DM Avun [oyc raise CO.5 ea3 s<=> */s REFERENCE Seabrook 15-22 to IS-28 Seabrook'85-1 SI LP EO 7,8 l L 013/000 K4.01 3.9/4.3~ h f>13/OOO K4.12 3.7/3.9 f- 013000K412 013OOOK401 .-. . (KA' S ) I ( I ANSWER 6.04 (2.00) l i l Prevents Steam Dumps from shutting once impulse chamber. pressure l stops decreasing' [1.03
. Removes the arming signal generated-by a load rejection. (prevents, i subsequent instrument failures from causing steam' dump actuation) C1.03 -
REFERENCE Seabrook SD-21 SD-24 Seabrook 85-1 SD LP EO 2 041/020 K4.14 2.5/ K403 ...(KA'S) !
!
l
. - _ _
*
,
] '
+61__PLONI_SYSIEOS_ DESIGN,_CONISOL,_@ND_lNS16WOENI6110N' PAGE 120:
.,
..=
. ' ANSWERS -- SEABROOK 1 -87/07/28-BARBER, ,
I
.
ANSWER- 6.05 (2.00) Prevents closing a supply breaker unless the incoming supplyfis !- I in synch with the bus. 00.83 i The RAT synch check' relays.are in service.at.all times C0.73 because
' '
of the breaker's automatic closure feature..:CO.53 s REFERENCE !
,
l ~ Seabrook- 4.16KV-24 1 l Seabrook 06-5 4160V LP EO 7,9' l 062/000 K4.03 2.8/ l L 062OOOK403 ...(KA*S)
\
'
.
f ANSWER 6.06 (2.10)
.I 1 increase.
I b.-more negative ] c No effect 3 items CO.73 e l REFERENCE l Seabrook Instrument Failure Manual . Section K, po 5,6,8,9 Seabrook 85-1 Excere N1 LP EO 5,6 015/000 A2.01 3.5/ SOOOA201 ...(KA'S) ANSWER 6.07 (1.90) The affected EFW line's motor operated flow contiol valve will shut CO.43 the unaffected EFW motor operated valves will'be blocked open CO.53 to ensure. isolation of the affected.5/G CO.33 and to ensure feed flow to unaffected S/Gs CO.33 b. tlain Control Board-(MCB) OR' computer' alarm.CO.23 AND-Status indicating lights 'out (No red or green-lights); C O. 23 ' l l REFERENCE Seabrook _EFW- PT-1 Sec 6.9 l L 061/000 A1.05 3.6/ . I l ' l l.
1'
.
L - _ _
___;-.__._--._ --
, y
, .
-I
: .. . .. . . =
... ...
s6.,- PLANT SYSTEMS DESIGN g----- CONTR OLi
- AND~ INSTRUMENTATION.: .PAGE 21' --------------- - ,, _ .- . 1' ANSWERS.-- SEABROOK/1 -87/07/28-BARBER, S, .,.
061000Al'5 0 ...(KA'S) .a
,
.j l
l
>
j
.g
.s
.
u' d
-l a
l I I i I
.1
.
.
.
l ' i ! l . l-
_. .
, , . ..
PAGE 22;
~ 6 7. - ' PROCEDURES _NQRMALi_@BNORM@L2; EMERGENCY _AND **
BODigLQGlq@L_GQNISQL'
-87/07/26-BARBER, S.' . ANSWERS - .SEABROOK 1-l . ANSWER 7.01 . ( 1. 50).
-[0.53 Trip all RCPs CO.53 RCS subcooling EO.5T q PZR level REFERENCE l Seabrook E-0,-Operator' Pr. tion Summary l Seabrook 85-2 Emerg Proc LP E011,3 000/011 EA2.03' 3.7/ OOOO11A203- ...(KA'S) q ANSWER 7.02- (2.50) Remain at power Shutdown Shutdown Trip Shutdown 5 items-at CO.53 ea . - q
REFERENCE ' Seabrook OS 1210.7, pg 2 L OS 1210.5, pg 1 TS 3.4. OS 1212.01, pg i TS 3.6. OOOOO3G010 OOOO26G010- OOOO69G011 . . . '( KA ' S ) L OOOOO9A233 l ANSWER 7.03 (2.00) l
[0.73 ea.
l Open, All Rods in
[O.63-j t
- REf
- ERENCE E Seabrook 05-1000.01, pg 4,7 Ssabrook 05-5 MPE-H/U LP :TO 86-5 SR Cabinet EO 4 PLT GEN 7 3.5/ l
_ _ a
,.
,_
'\.
,u
;4 PROCEDURES -' NORMAL t. ABNORMALtiEMERGENCY'AND~ ,
LPAGE: ?23
'~
BBDigLQGlg@6_ggNIggg ,
, ,
ANSWERS - SEABROOK 1 -87/07/28-BARBER, S . ANSWER 7.04 (2.50) A RHR pump suction' shifts to the'RWST- ' E O. 73 : ( Pressurizer. overflows"out the vent' E O . .7 ) ( E O .' 5 3 A EDG starts but does not load ' FWI isolates the S/G recirc.flowpath- JE'.53-O )] A CRV recirc fan / starts EO.13: a
!
REFERENCc 3 l Seabrook LER 50-443/86-002-00,. Inadver. tant'SI,112/24/86'
-d
'
Seabrook'85-1 SI LP EO 9 , 013/000 A2.06 '3.7/ l i
. 013OOOA206' ...(KA'S)
l l l l
."
..
)- l ANSWER 7.05 (2.50) l l . Using the atmospheric dump valves' ] 2. Using the EFW system 3. Using the pzr heaters 4 By adjusting the cooldown rate L EO.253 and ~ seal :irijection I flow rate EO.25] l L , Using a pressurizer PORV 5 items E0153 e resurize i l REFERENCE l Seabrook OS 1200.02, pg 16-19 ,
-- . -
( Seabrook 85-5- Control Room Inaccessibility LP TO11,2 I 000/068 EA1.12 4.4/4.4 l OOOO68A112 ...(KA*S)' l l l L I: l l ' L i -.- -._ _ _ _
<
qqq ...
-
, -- r-- .
q
,
s
. 3'
.nT;,Tm ,, [j ,
, , 1.j;
,.
,
' 4 :7_ _-P_R_OC_.E_D_U._RE..S___! N_O_R_M_ A_.L.a.c,: A_BNORMAL' EMERGENCY AhM-
'
, ,
.P. AGE 24-
. _ .
. ,-
BODl969Glce6 JQNIBQ(l ,.
-
n :.
>
' . . '
l
.
'
' -87/07/28-BARBER, S.' ,
,
, :ANSWERSf- 4SEABROOK d'
'
't u .
.o :
ANSWER 7.06 (2.50) : An unexpected rise in and SG narrow range 11eve CO.6] l High radiation from any SG.steamlin j- 10 0.'6) j
..'.
High radiation from'SG. sampl *
;[ 0. 6] L ::!
.
-i:
i :.
.j )lt -
Manual ' restart of 'saf equards equipment J may[6e -(,- .riecessary;- ,COk'ig;' e, .;. q
'
.
, !
REFERENCE Steam Gener ator. Tube Rupture,:;;pg l 2,'d!, , l Seabroo E-3, - q EA1.01 4.5/ d 000/038 I, - OOOO38A101 ...(KA'S) ..
,
. .\. J I 1 s- ,di r . .
l
. .
.,
,
l .
,
ANSWER .7.07 (1.50)
?. The workers are given verba1Mi' instructions and-precaut' ion LEO.53 Continuous health physics covera.ge is provide '
3 ,. , , .CO.53 l The' job is documented on an:RWP'upon completio .jL 4
~CO.53. . !
, :
REFERENCE ' Seabrook RP6.1, po 5 i y- .j
.n I
'
.
s ~."1
<'
:i Seabrook 85-3 Rad Prat LP EO 3 y n .,
194/001 K1.03 2.8/ V l
't .l
,
'
> 31 )
( i
..E I' )
,
.,
:// - }[
.
'/
-_
!
.:s, :
'\
,
4, ,
! . .'
'
>
,_ u
>
..
') l y r j ,'1
'
. 'l t : ,
,4i
) 'q
'l z i6, +
,
u
,(<
0, p l .h
.... - i__ _ '
_
'h/ - , e
' '
, - _ _ _ _ , . Y 1 +
..i . * .. .
.
6 ADMINISTRATIVE PROCEDURESt _CONDITIONSt_AND_ LIMITATIONS- PAGE 25- , l
' , ANSWERS -- SEABROOK 1 -87/07/28-BARBER, ; -
i
, ANSWER 8.01 (2.40) Site Area Emergency CO.43 15c. Due to a LOCA (E-1) [0.23 ( ' b ,. Site Area Emergency EO.43 6e. Bus E5 and E6 cannot be powered by -]
r offsite or onsite power within 15 minutes (0.23 ;i i i ca-Unusual event LO.43 due to transport.of contaminated individual from' onsit e to an of f site hospital 00.23 .!
!
7L [sGeneral hl*,. b(TA [rwgW)E O. 4Z'3(% l Emergency orange and 6e. Containment pressure of.22 psig and imminent loss of offsite' power with one EDG inoperable. E0.23 ]
-I GRADER'S NOTE: GIVE 75% CREDIT IF EVENT IS CLASSIFIED ONE LEVEL-HIGHER !
L AND APPROPRIATE JUSTIFICATION EXISTS FOR THE CLASSIFICATION
i
,a REFERENCE l
, Seabrook, Emergency Cl assi fication Flow Chart, ER-1.la ! ' Critical Safety Functions status trees Seabrook B5-3 EPIP LP EO 3 I
.i 194/001 A1.16 3.1/ 'l 194001A116 ...(KA*S) )
.1 ANSWER G.02 (1.50) J i
Any work of an emergency nature (priority'"E" work request) may be I performed C1.03 if approved by the Shift Superintendent CO.53 i REFEHENCE ) Seabrook Station Maintenance Manual, Procedure MA 3.1, Work Request ;
-!
,
'
ANSWER 8.03 (1.60) s ppm . CO.53 All ow f or decay of short lived radionuclides (minimize decay heat). EO.53 Immediately suspend core alterations [0.53 or positive reactivity changes. [0.13 l'
REFERENCE Seabrook TS 3.9.1, 3.9.2, B3/4.9.3 l l Seabrook G5-5 Refueling TS LP EO 1,2
s.>
' ' , .
,
'
t,
- i L . _ _ _ _ _ . - - . - _ _ _ --_.___ _ _ _ _ _ --_. . .,
T'. . _ .
'
'
_l ,_ ,. ..
:'f
'
,
.
.a .'. , ,. .. '%g
.
.PAGE 1266l
. .
.
* Bt__8Dt!1Nl@lB911W, P{QCEDURES9 CONDillQN@i4@NDJjltillAllONS c
;,.
y , >g ., ANSWERS.-- SEABROOKi1 ' -87 /07/282BARBEi}, .
..
, x
'
y:
~j 034/000 G5 2.8/3.7-
'
s
[.cf /) 8 d
i)
' . E
,
*t ,,
b r# ,j- - , ANSWER 8.04 (2.50)- 3 t
: Fuel oi1 day tank ,
-
..1 Fuel oi1 storage' tank l
,,J Fuel oi1 transfer pump:s <,- .3 2 i t ems C O. 6] e '
,i
.00.7 jb. Check.for snow drifting over.the. diesel generator.. ex haust' st ack-
.
'
( '
,
'FiEFERENCE .
Seabrook TS.3.6!1.1-StandingOrder86-013f + Seabrook 86-5 4'1$0V & EDG'LP F;O ,13
/j; 064/000 GOO 5 3.0/ ,
#l O 400(4005/ ...(KA'S) y
/- t ( '
. .'j
,
;
'
\
<
, r- ./ '
{
} _
ANSWER e.05- ( 1. 50 ) ,.y No 00.23 Ops keys will tA utored in a ' locked control. key cabinet 00.43
bI Access to the area should be restricted CO.53 and-the lock must be changed at the earliest possible time coincident l with plant '
/ conditions.'C0.43
,
,
REpER?)t4CE 4 E Seabrdok OPMM, Ch 7. pp ,)s
'I .
,'
(4 194/000 A1.03 2.5/, A103 ...(KA'S)
, j .s l >J ,
,A<
-
1
- e ,
I I, i: N b i h +/ .e f' a : ,/ a ; ; l , 3':; 4
' 1
, ,.
i
,' '
*
1 4 . , jk Q y-
<
<
.
w 4 l , O , j l A s .c ' ) n-i '
#
'3 / j
.y
-)
.
;:
, p
\ fr ~,,.4 :. ' 4; d' c) _,i '
'_ _ Y dh} - - - - _ - _ _
. _ - - - - . . - -.
.
.
- ,
e .
. . .
PAGE 7271
. . . *@t__@DylN1@l6@lly@_P699@Dy@@@t_ CONDITIONS t _AND' LIMITATIONS'
g, . ANSWERS -- SEABROOK 1 -87/07/28-BARBER, . ANSWER- 8.06 (1.50) a. Pressure Volume Isolation valve open CO.33 and power removed CO.13 Any 2 items E0.43 e b. No EO.23 Surveillance requirements do not have to be. met on inoperable 1 equipment EO.53 REFERENCE Seabrook TS 3.5. TS 4. Seabrook 85-1 SI LP 'EO 1 006/050 GOO 5 3.2/ OO6050 GOO 5 ...(KA'S) ANSWER 8.07 (2.00) j a. B b. B i c. C d. B [0.5 ea)
,
REFERENCE , Seabrook TS Section 6 OPMM, Ch 2 oP i2 coo 2 Pg.3,4 194/001 A1.03 2.5/ A103 ...(KA'S)
,
%
.__.m_~~
._
_ _- ._ _
-
s
. "Bu__0901NISlB@IlyE_EBQQEQQBES,__QQNQlllQNS t _8NQ_LidLI@llgNS PAGEc.2BJ4 ,, .' ANSWERS -- SEABROOK 1 -87/07/28-BARBER, q i ,
ANSWER B.08 (2.00) s The intent is not compromised. [0.53 There is no note in the procedure requiring. steps to be performed in sequence. [0.53 The applicability is stated in the procedure's body 00.53 OR the responsible dept supv. initials the non-applicable step .
'
that need not be performed. 00.53
>
REFERENCE Seabrook SM6.2, pg 12 i 194/001 A1.03 2.5/3.4 . 194001A103 ...(KA'S) I
!
i i '
!
!
i ! ;
,
!
_ _ _ _ _ _ }}