RA86-023, Forwards Comments on 861217 Senior Reactor Operator Exams. Related Documentation Encl
| ML20211N049 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/23/1986 |
| From: | Kelley L FLORIDA POWER CORP. |
| To: | Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20211M941 | List: |
| References | |
| TRA86-0233, TRA86-233, NUDOCS 8702270427 | |
| Download: ML20211N049 (29) | |
Text
{{#Wiki_filter:__
' gM MJZ.
ENCLOSURE 3 7Ysf//f 00 O. Power C 0R PoR ATION December 23, 1986 TRA86 0233 Mr. John Munro Chief, Operator Licensing Section Region II U.S. Nuclear Reg ul a t o r y Commission Suite 2900 101 Marietta Street, NW Atlanta, GA 30323
Subject:
Crystal River Unit 3 12/17/86 NRC-Issued License Exam
Dear Mr. Munro:
As per the current practice f or examination revie ws a f te r NRC-issued operator examinations, please find enclosed our review and comments on the De ce m be r 17, 1986, Senior Reactor Operator Examinations given at Crystal River Unit 3. We are including our comments and recommended action for each question under review. If you desire any further information, please contact Mr. Johnie Smith, Nuclear Operations Training Supervisor, at (904) 795-0504, Ext. 107. Thank you for your at tention in this very important matter. Very truly yours, c KdL LaMrryC. Kelley Manager, Nuclear Operations Training JCS/LCK/lb Attachment 0702270427 87021 PDR ADOCK 05000302 V PDR NUCLEAR OPERATIONS TRAINING DEPARTMENT: 8200 West Seven Rivers Drive e Crystal River, Florida 32629 A Floada Progress Company
o The following comments summarize items noted by the CR-3 staff during a review of the Senior Reactor Operators examination given on December 17, 1986, and are submitted for y@ur consideration in grading this examination. CATEGORY 5_
@ESTION # 5.09 COMMENT: This question requests that the operator " State the two (2) most positive indications" for a loss of natural circulation. At present, there is no approved reference which defines the two most positive indications". The reference listed (B&W Technical Document) has not been approved by the NRC for operator training and therefore cannot be used as a stand alone reference.
RECOMMENDATION: AP-530 lists the indications which the operator should use to verify natural circulation (see attachment 1). Accept any two of the indications listed.
@ESTION # 5.10 COMMENT: See comment and recommendation for 5.09 above.
@ESTION #5.22 COMMENT: This question request the candidate to supply a list of symptoms for a specific plant condition without adequate information to identify that condition. While it is granted that due to the recent emphasis on this condition, the candidates on this exam most likely identified the correct symptoms, it would be unwise to assume that the same will always hold true in the future.
RECOMMENDATION: No action is requested on this exam, however, it is requested that this question be reworded prior to future use. CATEGORY 6_
@ESTION # 6.02 COMMENT: This question states "Setpoints are NOT required." The answer key i lists setpoints.
RECOMMENDATION: Delete setpoints from answer key. 1 I
r . i
@ESTION # 6.10 COMMENT: To answer this question, the candidate must assume either a bare GM detector (as they would be with no special features), or the instruments actually in use at CR-3. The question does not specify which is correct. While the answer specified in the key is correct for the first case, all instruments in use at CR-3 are designed to prevent this occurrence, see attachment 2.
RECOMMENDATION: Accept either answer A or C as correct.
@ESTION # 6.12 COMMENT: This question requests five diesel start permissives. While it is true that the conditions listed in the key must exist for auto start of the diesel, there are two additional conditions required by the diesel start circuit, see attachment 3.
RECOMMENDATION: Add <6 psig lube oil and <250 rpm to the list of answers and accept any five.
@ESTION #6.13 COMMENT: The DC and SW system surge tanks have a dual " relief" system. During operation, bleeder valves (shown as relief valves on attachment 4),
will relieve excess pressure to the waste gas system. Operation of these valves is not considered abnormal. The safety relief on the tank relieves to the ventilation system through filters. RECOMMENDATION: Change answer key to read: Vents to WG system Relieves to ventilation system. CATEGORY J_
@ESTION # 7.03 COMMENT: Question states " State one (1) of these three". Answer key lists three responses with a value of .5 each, (question is worth 1.5 points).
RECOMMENDATION: Accept any one response for full credit.
@ESTION # 7.04 COMMENT: At CR-3, the use of service water to feed the OTSG's during a loss of feedwater is not a desired or workable alternative due to plant design, see attachment 5.
RECOMMENDATION: Delete question from exam.
QUESTION #7.13 COMMENT: Response "A" should be 24" vice 30", see attachment 6. RECOMMENDATION: Change answer key as indicated. QUESTION #7.15 COMMENT: Question asks for two actions which are required prior to securing a RCP per OP-204. There are actually three actions, see attachment 7.
- 1. Reduce to <607, power.
- 2. Assure that TC is selected to the unaffected loop.
- 3. Select pressure control from the loop with one RCP.
RECOMMENDATION: Allow full credit for any two of the above. CATEGORY 8_ QUESTION #8.03 COMMENT: Question asks for five events which are reportable immediately or within one hour. Answer key does not address requirements of 10 CFR 20.403 which contains immediate notifications, see attachment 8. RECOMMENDATION: Add 10 CFR 20.403 requirements to answer key. QUESTION #8.06 COMMENT: We do not feel the operator should be held responsible to list this type of information from memory. This is not an item which the operator can control or one which will affect the ability of the Fire Brigade to respond as long as there are a sufficient number of qealified members present. Also, Building Service is the subset of Maintenance from which members are drawn. RECOMMENDATION: Delete question from use on future examinations. Accept either Building Services or Maintenance as correct. QUESTION #8.10 COMMENT: Second part of answer should read: Nuclear Plant Manager or " Man On Call", see attachment 9. RECOMMENDATION: Revise key as indicated.
. QUESTION #8.19 COMMENT: The double valve protection guidelines have been rewritten. Also, the requirements in the exception to this rule are reworded. Both are recent changes and may not have been reviewed by all candidates as of the exam date, see attachment 10. RECOMMENDATION: Revise answer key to accept either wording. GENERAL During review of this examination, it was noted that several questions, particularly in category 5, referenced documents which are either not readily available or approved for use. These documents include the B&W Technical Document, Emergency Procedures Technical Bases and the training material utilized at other B&W plants. While it is true that most of this caterial is common to each plant, there are those areas where d3 signs differ. We feel that questions used on the examinations should come from the caterial supplied by Florida Power Corporation. If additional material is needed to write the examination, a request should be made to Florida Power Corporation. I e
jv .c x NC REV 05 Date 10/03/86 AP-530 4 ,- 4 FOLLOW-UP (Cont'd) 1 ACTIONS DETAILS .
- 5. If adequate subcooling margin Establish HPI:
does n21 exist, THEN:
- a. Establish HPI a. Open:
o MUV-73 o MUV-58
- b. Ensure required OTSG b. Start 2 HPI pumps levels
- c. Refer to AP-3'80, c. Open:
Engineered Safeguards Actuation. o MUV-23 o MUV-25
, o MUV-24 o MUV-26 Required OTSG Levels W/O RCP CONDITIONS LEVEL o Adequate Subcooling 6 5 *$
Marcin o Less Than Adequate 95*. refer subcoolino Marcin to AP-380 o L2 HPI Pumps 9 5 ** Available
- 6. IE natural circulation is Verify natural circulation by verified, observing:
$ HEN go to Follow-up step o Tc =TSAT of OTSG.
17. ( , o AT (incores - Tcold) develops l and stabilizes o The average of the 5 highest incores follows TH within 10*F. ! o TH, T e, and Incores lower when OTSG pressure is lowered. l 1 l AP-530 Page 5 of 13 NC l i I l
f m FIDRIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 NUCLEAR OPERATIONS TRAINING DEPARTMENT ? - i i PROGRAM: REPIACEMENT OPERATOR TRAINING * - i COURSE: MITIGATION CORE DAMAGE - LESSON: RADIATION MONITORING ' L s l LESSON NO: ROT 12 LESSON LENGTH: 1 HOUR REVISION: 1 DATE: 9/3/86 ^
~,~
N 6 Prepared By: , 4)# > Nuclear I tructor~ - Approved By:_ t . N Reviewed prior g use: (/ Nuclear Training - Supervisor Date Instructor Signature
^
Reviewed and s concurred with:
'Nucleat Ope 3tations - ~
Training Support Supervisor q JW
- ec y u e
--'-~l
. monitoring, it is important to know that a very high input rate may paralyze the counter: as the input rate increases, the observed count-rate reaches a flat maximum, stays fairly constant for a while, and then drops . ' h j8-3) ~
Some G-M detectors have a built-in holding circuit. The function of the holding circuit is to take the detector resbonse, once it reaches about 3/4 of full scale,7to a
- full scale value-and hold it at this value until the strength of the radiation field is reduced. Whether a j.
G-M detector has a holding circuit,' or not, saturation
- in high radiation fields does notliamage the detector. '
i
- e ,
- - - The detector will recover once the high radiation field is reduced.
2.1 BEHAVIOR OF SCINTILLATION DETECTORS IN HIGH RADIATION FIELDS
- If the scintillation detector is used as a pu se-type instrument, similar to the G-M detector, the resolving time, , is on the order of 1 second. ' A random coincidence describes an event in which two unrelated 6
-rays (i.e., not belonging to the same l
, disintegration) are detected within the resolving time of the detector. This effect could result in detector saturation similar to that of the G-M detector.
However, due to the extremely short resolving time of the scintillation detector, saturation is not considered very likely in any radiation fields that could exist in Page 8 ___m_ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
4 Mddd hk
, ,.3 -
ANL-7291-REV.'l
/ =
?
Radiation Safety Technician Training Course C ..
.T: ;- .
.q, r
- by .
v
; sll
- .,: h -
j ;W *
- 'r ;~ ,
,/ .
a: p Argonne National Laboratory 6, (voW Argonne, Illinois
-- " ,y'jx _
- i?" ,,
.s
;g: , , ;fc
'. .. 7
,, ; ,p _
, y
./ ;
;, : y
{ _o V
. 4 1
g ,.e s;
~
O U.S. DEPARTMENT OF COMMERCE National Technical Information Service s .
--..--------c.m., -._ y - --,--, -
l:. r f 286
- ?
Pulses formed in the counter probe are fed to the c' rate meter circuit. The meter reading then gives the average pulse ra in the G-M tube. With these circuits , the device needs no zero cori
? or warm-up period._ However, some counters " saturate" in a very_
r rad That is, the pulse rate becomes so high that the c8
; Crate circuit fails to function,properlym_As a result, the meter readM
*; zero rather than off-scale [ The condition of saturation caC'
~~
ruin the tube ~becabse of the rapid loss of some types of quenching i The G-M survey meter may be used to detect beta gamma . The tube thickness is about 30 mg/cm2 This is much too ' thick to allow alpha penetration, but the device detects beta of E >M, ! k 2 MeV. The sliding shield (~1500 mg/cm ) rejects all beta from norm h.
- sources. For low-energy beta, an end-window type G-M survey me'"
can be used. In an end-window tube, one end of the cylinder has a [ very thin covering, which can be used as a window. Mica , a few thick, is quite often used as the window substance. These deviced
.]
- f. spond to beta of E > ~30 kev (22)and alpha of E >~3 MeV.(24)Since window is very fragils, care must be taken in using these ' devices. ( .:
End-window counters are used extensively to detect [
~14 k C, which gives off a low-energy beta. We must be always awarej l of the highly directional beta response for both the end-window type, and other G-M survey meters. The G-M survey meter only detects beta if the open area in the sliding shield is facing the source. $
.b. Energy Dependence y The G-M survey meter is not a precise instrument f ,
exposure-rate measurements. The response of this device is not di-h rectly proportional to the energy absorbed in the sensitive volume.(3%. s. 1 The energy absorbed per unit mass in any medium is a funcdon of the. - N photon energy fluence (t) and the mass energy-absorption coefficientj ( en/p) . I This is true if the secondaries do not have too high an 4 j energy. The count rate for a G-M survey meter depends upon the f j' efficiency of the counter (counts per incident photon). This, in turn, is a function of the cathode material. Regardless of the cathode sub g ~ stance used, the count rate for a given exposure rate is not constant a,sj photon energy varies. Thus, the response of these instruments in terms a r a
- l.
i -
8 4 4 l 5 'l 6 _7 i
- r. ,
1 F T 7 9 f 3 b Un MO) 34 ka N N m
-S- 5 /5 5tf e 90 PSIC g-* O Cev ?77) i t w - 4<1)
, 14' 6n 500 y y n
y $ 3 3[ Grt-;,r) Q.8.L*].2) WM-C ' ,/ f g $. M
~% ums 4 a
c c c 1 l.
.ac. RELIEF 4-6n- t rO en eo 'y ^Ju, w i> ; '3c--m> (n -I ' '
@ t,.- W m
- u. "'y'k) X a
@g~'
i va g y .. .,, g Fs,rc tn. , 3 ,4
-<+
e.,-20 v7>}g-
, x:AY , .,s
- 9 3m .. >,.
y U a . 4
" "' i 3. UL.0)
[6n sc0 in. g ig i I C* W -. C r< 2^O 14-3
% gg,g gg CAPAUlf 12 i t en 2m)
! ? 2 u NUCLEAR SERVICE CLOSED CYCLE t
[Q]39, 3 1 5
? til gnfg hE ," 14' S
~
s,s en n ,,,,.,,.,. gcn m-) A g-j I O ~m) Myl2 A 38' ** W H ICn-1?O rr ,,
)
, 5 i i 14* 8' I'- 13 i g [ (sn- s t a)
* - ~ ~
(s n-4 t O
%(;sv- ?^r) y - - - En-4 r) .
. 6n-4?O T.m 6sv 492)
> cwk '
On-4tO ( se- 5 ) l }j(i}i H- ss% G a 2 r g, g) i (
%Ge< 7c0 NUCLEAR SERVICE F
C. C. CCOLING PUMPS (4% 7 vt 15? D4 E900 t,PW G 110 5 I.t HW H- { Tu J
, Gn-aza E ..-
'yggjg/
v . . . . . . . . _ .
, 1,.
16* _ _ 16' L ev- 14 4) m_ ,y - e
~
T e o . 5 EMER 3 4 0
's O o G d c c
+b +bd+ +b d+b +b d+ . H+h i
h 1 O [ Cn-Irf)A n -9 ? f h- 19)A -
= n
- a. y b d[
g
/\3 N -
12 % db 10 4, 0 azu k g egp 7, A, q_ [ 1 qu 10 cn uO ,'--* *-[Jis,*s4,Mi.-* v .- p 3 .s Eii( I o Ei@ k. r
- k. 2 ). n i .y .o u r u , ,,, ,. . c o ,. o i y
r k. 2 08m " s a - 1 5 _I c-E Ita ;n) It- "9 _ nenghi4e 4h> _I e-so te-r) I , c- "o g AM p ,,_ g Ior 2 rms 11Pr vino n e cm es-cn n DRA:n VENT ,} /q 9fh */ 4 gang 5 y ,,- js4.t visw e en ea;cea n
!? ty r.
3 at v i sc3..a c.3 n: en es- oc e aun..m. a 11 as-9s t t? PE A '8h4 P I - ?- 61
- 1 NUCLEAR SERVICE
, ,T HEAT EXCHANCERS a. FLORIDA POWER CORP (
I ' st. PE*tesser. # Lou'ta CRYSIAL river PLA wees
'iECLlAR PIPING S. W.
tu it VT f 120 12I ($sv-4 ? )) w NUCLEAR SERVICE! 4 t. ' CLOSED CYCLE C00Ll WM 1 m 16' _ isi .e &temat etsiew easts ccer conssts g- p[;aswN (M C&O seeme...= M ... E
.ne)# . YsT U
lO 4 gi, h h !bd"'"' ~
1 I 2 1 3 l' 4 f 5 ' C < \ O^ .
,e
'a N C'. V et
~k 33 99) r7
[$ E* 3 l ! VIk1 i M *) hd3
'/ 'v (r 9,,
h![
.f 10 '}
(N #5)CD I k5\ 2 ' *) '
.)T bg O's ss ) { Ls 5
!.5L p_0 k ( l5 a g Ccv 140 [b y[
B - }' v
- "J.b wqa 2 C pp/
H 'i "9 c e
.x ,. , - -
a-VUb /g / e(;xv H : di neta. 4g M7 gME}' # Ou
!) l m
['2S (rv 5.4 )q !I 4 1[ lCrR,- [t <w r_s% VECC1CV '81) H-
'" 7 g DECAf HEAT CLCEED CiCLE*
SURGE TANK 12.W d' '
%! T ti M 38 (:a 94 ) g 03-is!) ,g LTT MA: ado 3 rg n ) H)--4 y g
(' r n ia ) y 58)
,4g y'dI Kb vm eg. i;7) , ( "M Co e if:--lF 53% y a'y!]. e. g3 g e:v.is2)v tc< 22 ) 1151 DCCAY HEAy 2.
I # Ug3 ,, )\ (n. % D. k/ 3 SERVICE (;* - 53 ) (;. v s a {3s:s r, \ _. .,2 g' 98 /*\ CRAIN I g H] Ccv ?4 [7(g SEA WATER
-Q/3 =p' N,{(7 y o) g ( r, :c )
L412L (.p si. 6 38 C -
'M "1 J s .' PUMP M310R i
.'F 1 ,MJa0 Iq;~8 e '4 g._ 'tng
-- H ca;n '
] l CCv '72) Y C df )
. a }a,MA<+- -
C;v-es ) c;v . ;
<- , P,l Y M rigg i n F,
7
*6:va ) IFTP T6c< 79 )
D (sh
, eo L2
-H FiD *-l
/ )
, ,,, [jpgTT m"': 1 EZD 3g & ,
Oy :s ) w o e O DECAY HEAT CLOSED CYCLE COOLING W4TER PUMP e:v :)Y W vEM
,[
t LC CPJ e !) f !.60. , H (n ?l.) j ~l
+-IIL r
~
=
C:esa (\ <fWW h ' Asm rm . e kd" Ca "OZ g44 f 0:v 4: @)' FT, , La 4C v '0')i 3 C H -(- g lta.tr.) C $ 2' P
'F!:* g)i 2 Q Y.1Ccven kd ' "2 -
! '.s L .;
> a hh; *GT@{,<
c -- ri o to; eOVL u2 1 i C.vM) '>< (y v s s it
-(
Tr ,C&u) {w Ti' __."
* ' ' ~ ~ 3e
- i[
ca n ) ' , [X}-Q-b 1' N,7 (v .) ._, ( 5 wTfL* , h g' L~va* ) e.f 2-h (- re ) 33 [g;
,_u) i f,,pe pt
, Qgh> < aessi usr
( .e,y) p U"" *) H ~ ~ DECAY HEAT CY AT
,b tevP ) l ti s-- #
n 6 v UMP C w EXCHANOER A DECAY HEAT PJUP i ; 'r y, . ) AIR HANCLING LNIT Da A W r y . , 3 ,) e _{_r , .g
$?Oe.v-u 14 ccv.no H- JE r- ,- 38 ~
T ~. \4/ (k
.g - -- Mv ;6 ) 53f?., l 3:.na; ,
(b _/aT 2 v c _, H _. i c ,3 A+ c I [HiK v " ' ' " -
")
3 I rwgp;g[P'"N)Nr ,
~~
g_,,,) o hv enT
-iM M-)+
i C' D. v e) [ Eb e '3'
" i n,. ao H-.
dp ' g_f] 1 A4 av ((p
'g- y S O:v- r0 ,6
- O * = =
e a
-m- -
O FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 NUCLEAR OPERATIONS TRAINING DEPARTMENT PROGRAM: REPLACEMENT OPERATOR TRAINING COURSE: SYSTEM TECHNOLOGY LESSON: DIESEL GENERATOR LESSON NO: ROT-4-6 LESSON LENGTH: 4 HOURS . REVISION: 3 , DATE: 10/9/86 i Reviewed Prior.t2 311g: PREPARED BY: Vm1d _- 'm l Nuclear Instructor l Date Instructor Signature
- REVIEWED and * '
l CONCURRED with: - Nuclear Operations Training Support upervisor APPROVED BY: - 1AL C . [NuclearTraining Supervisor s l lO 4 i i
e o e v Yk h 2 a8
==
3
> ~
,n
- ma k
O _ V rs ;v x 8 O 4iI 3. z
! Or3
> ; faa
,(- r5e
= -
i, is ,- o a- z -
. a-so
~~
$r I- *"
b; y
=
8! it si .e ,, fg= my
** s. <n re -Q
. =,
z i '!* b m
. ::' g w
o j
*s -
97
- d.e
. ~
-l' .
iI
$ Gi -
set w a
=
m 9 c i ( a- g v h h 6
- e
* "S H x
. M ! ~* a2 ..
wo H< s s.A .- m
. e
-T O
< e O 4, g 7 ~
- b $
x as esu EeS 3 - e foa o* p i. p #iE e f/ 83h ll II 0 t/ if a e m w *{ Il Ii e ei es i h
-f - w Cf- +
w
-il 'l -
/
o 3 l H' s FIGURE 9.0 $ i b-Ov l
+ 1 ROT-4-6 Page 65 e
NOTE: A locally started engine will respond to a remote (control h v room) STOP cosaand. With the "43" switch in ' MANUAL", the affected diesel will not be able to respond to an ES actuation, or loss of power to the ES bus. With the "43" switch in ' MANUAL' and the RS1 switch in
' NORMAL', only low speed (300 RPM) remote (control room) starting of the diesel is permitted.
There are three " auto start" signals:
- 1. ES actuation (HPI)
- 2. ES bus degraded voltage -
- 3. ES bus undervoltage (loss of voltage) ,
Permissives required for " auto start"
- 1. DIESEL START MODE SELECT switch (43) on main control board (one for each diesel), selected to AUTO.
- 2. Air shutoff valve (EGV-35 (A) EGV-39 (B) open.
- 3. CONTROL AT ENGINE - NORMAL switch (on the engine gauge panel) selected to NORMAL.
- 4. 86 lockout relay (generator control cabinet) reset.
- 5. SDR seal-in reset (accomplished by pressing the RESET push button [PB4]) located on the engine gauge panel.
s O ROT-4-6 Page 11
/-.--
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 NUCLEAR OPERATIONS TRAINING DEPARTMENT PROGRAM: REPLACENENT OPERATOR TRAINING l COURSE: SYSTEM TECHNOLOGY i LESSON: PRIMARY SUPPORT SYSTEMS REVIEW ! LESSON NO: R07-4-2 l LESSON LENGTH: 4 HOURS i REVISION: 1 DATE: /o//J/F4 O l Reviewed P.gigI iQ 233: ! PREPARED BY: MM Date Instructor Signature REVIEWED and -
./
CONCURRED with: M tHA QNuclearTraining Supervisor si APPROVED BY: e le6'
" Nuclear Operations
( Training Support Supervisor 1 w, C hh .ML cm to/a sju g <
y _ _ . _ _ . . . . _ _
- . _ . . _. . - . _ _ _ _ . .__ _ _ _ m l :- -
CHAPTER 1 cooling water flow through the HX while keeping total DC l j O flow constant. These valves are controlled with a manual I i
~ confroller in the Control Room or from ES 4160V switchgear rooms A and B. The bypass type regulator is used instead of throttling flow to the HX to maintain total DC Systes
- head constant. The bypass valves fail shut to ensure any l valve fault will result in full cooling flow to its HX.
NOTE: All other DC coolers are regulated by manual valves on the outlet of the coolers. 1 1.4.4 Surae Tank (DCT-11 and -13) ) 1 A 5000 gallon pressurized surge tank is installed in each system. ; The tanks are pressurized with nitrogen to prevent pump cavitation. Upon reaching a pressure of 13 psig, bleeder valves t
- l. vent to the relief valve header through charcoal filters. Nitrogen is added to the surge tank if pressure falls below 5 psig. The tank may also be vented to the vaste Gas System if the system is contaminated. The surge tanks are located in the Rest Exchanger Rooms of the AB on EL. 95' (Figure 10).
1.4.5 Eining 2
- a. DC - Velded carbon steel,
- b. Sea Water - Flanged carbon steel with PVC or polyurethane lining.
ROT-4-2 page 5 3
- - ~ . . . _ . - . - _ . _ , , , _ , . . _ . . _ _ _ . - , , _ , _ - . _ .____.._...__..____ _ _ _
- v .-i
- .,-.e I g 5 -]
.f:\,: Q G k y
'? .ef-R.. h *.- &
, n
, s. . y *u :'id e x L
;f , yv , m r s\ L. *a : W 'n ..er*.*,
l < - . Ja> i v; '
-;; g-' W ..U*y. 4 ;;e.;_]4 ,' 'V97, .
- e. Q f
- 4. y , ,
.Q , *
,%, - a, .
o . 4G , , , a -- p 5 'l _'s. y f I $ #
.y"3 - - - e ',u ,
4 % ,'g
, y.. 1. ,' < -
,- i s
- b i '
?% , s, , A ' ' - ' - *
.7 4{ t*, igg. ._
---- i .-
i R::- ? " ' } f 'l br, ' g > . . , . ,,, e , Ulth h p Q 3g
- W4 C'. Nj Q N ' -
b M: - q:> L.c w 1 W' A' !!U ' ~ <- I h CRYSTAL R VER ! ; R_ _. M.fNJ,. .- wm m.. w.
;- ' ' " ' t; ..jM Eu
, - x . , . ,,
.t
+
mA GM ] m./) ,'
~ -
i% - {1" 3 ' m .
, .* ::, , . , . * . a "1 _q,
,1
,e.,k .;
'y .4 N"' .-__P' h. g g
- ,kn, - ,
,h<r. **.,r i'r *
.h \ d g'~~* '/ ,Mp- ,
'e- -
t ;. !
; _l?c^ h ~'["
t
}r -k 'hs 5 ' * ' ' ' L'
- a. m -
c; .
- - - ,3
. , 4: .r 1. . . , : s -' '
e . :% . *y - qr 5.
- p 7! ,! : ' ';'
".. f f.::
,3.f.',.,4M p. 7_*. .~ . _ ,
..; .'+ .;
n 5 y. .ap .w 3 .; ** ;
- n, ..
,s <
;. q , .; - :: .~ p g .+y -k L
[lx .,l. lf E -. O '. k ' ' ,;l' ~*.:l..~
. ^l....,,s ;.:: .: , ..,
.(f..;
l.' l,l .;X., . .f ; . : : y.- 5 s W;b V.
. x.
- _ t- bf. &f'*.4f.*'..s? .
.... . . .m, ' . ,, ; a, . . - f., .: . . ,* .
..> , .y..
4 _._
..'. -. .. .. . .f.c.. g.
;. z. ..
a u,; -
. Q;. -' ': . - '.; *f ;
4-
- ,(-;
s J'. f.',f :. : >. ;
+ '_;
i 3
*- '" , . ~ .
,l ;y, ...l ::' -!_ _ , -
';. v
, . ew . . a.: 5 ,rn A h. ?
,< [?
.;, - ; N.:.. ; -
- , ' ? ' .x;
, , y, .. g r . ., - ..c ,z'i , , '. . y. _ . . . . . . . ' . s.. ... -
' 99 8'E ' \ M; '. b , 's.= i .D .v --
ggp '_-y* Lw y@*1.? > pN< , J 3./14:y[M
,W; f J; .'Og' ; ~ . ',7 y .3. .
i e. .'. '. . f M W "_ . rf 1 f y. g . ; *: p, ; ~ :s ' g:g ';L
'n
.a,,+_ 2. . >;. ....., ,-.y. .. .. . x .& .. n < , , ; 9:
.: 3 d,'.
.Q s .
~~. . ,,,.c .; n; w' <h m.
. f L g. .: .x.s..:
v.g %. . , ep.:f
,.~.- ~ . . ..&
,a ; m. . . ... , : . ~. . .. ,
.:2.m u. -
m py w- ,: . . ; e; _. yT.,. ~ _ c;n~,. . -e7.>s
- ~ t< n -
- 4. , . . . . :c
. .: < * ..:'- , ~. 3 ; y;,
-p;,w u . , -
3 g. .. m. - .
' *
- M 4; Y' '; .s'{
- + g-d, b .Av ./.. .f ;. .: #
7 ' .* x.~. .,r " ' . ' - ..
.b*yx/. .
-+
Q';y. !'.;', ,-{4: k - '
.'o.
ygg? V w ? m; :3.
~
y y m' n .
.? :
. t <.. . .
. ;& '. : .: . . .:. , :L. ; .". ': 4 2.wf. :,:,
4,,? 2 4%..,,.,t ;, y;. :'M., i,y ' ; A, ,7:,:n &p ,,'h;p.; Q ,[ , . ,. . ,' :
- 9. . .:. .W. . ,a. .1 ' y v. '_l .+e, y~ + s - lr & 2, S' g s .. j .: :.
y-
. ~+. A. - .**'
. ;, ,a,, '9
- p. .; ,. .j 'yn+> -eA L'- -,4,. ,
=si e A,~ .. -
, - q. p: .: + . _
m i , ' ! ;;g; . . a . : .D_ =
/T b' , ., .. _ ..
.[.:.% ( ',. - }: ,
-kJ . - .
.: . m,,: . - ,..
~ .- n 1[.
ea :: w qq- ', L 5^'*' , : w 4R. ,
,a 4, g a -~ - g
' i ... 7 ' . ';. [x'
- j ' ?
,1 '-- , - [ .,* gg i
'}., + ,
- v o ,
,;,y y, p _
\
2'f? . ^ n n,n - n, . w: :. . .
~ ~%b .1~~ W.t.. 1 p. . V 3
- n. '4
. 6.Us 3
* .y;; . ~. ey
=--
h:; .js "Q.W.
,n fn16 1-m,~c,,..q'.f,. . 43 'N' :;' ; ~._ _ .o. _ an. a - 4[ f:A:' -
yp w ;,...~ .2 .w. w; .
\gar %g;u[y ?;&a. mp.e ,o q[ <./
e. l: H - l- & anum xs%- ky?W .A. pf f' @O ;i f V, M [' h U .L ,g, f ' ..4 ' u "ak 1 Maw: & g'[' %m i og "M ' : ". > ,.. - _'%.Ek'4 : , ! '
. m -.3 i #N."*'u,.. gry .
_v e1 o sa mv m., 1 ,
- p .V. ., n . , ,.J .. , ,3
- g__ - _ ,( ,4 .J,-S j
- n. -
,R
.. . , u n. w
,t. < . <
n.. ,
' ~
, 1_ ,
- =
1 1J' , $ f .}; s.p' b 'm'. ';. 4 -Abnormal Transient Operating Gu i - Y -~; '4.. , , w: . #p, '.l -w nM ,. J,ATOG;, i
-i
.. ( . p,s%f 5.i; M M,p
, v :m m.
5= y ' - e'4 :;. y's , : * "A
,g ,v f. ' L] Jy f wJ 'ui;Q <n gx , y.
R ~( y , 4 us 3 y,..w,'c%,
- - m,T ?, '
- Part 11 -- Volume 2 .
i
=
< ~
J r 3 Discussion of Selected Trans.ients -
! .=
m, # p-s s a [.$ , 2, @N., a - # l 'M,
- - 4 x
~
1* h. mAhoo . . Babcock & Wilcox . .. ....., .......
]
, h t- $ $
~ .'
BWNP-20007 (6-76) SASCOCK & WILCOX .,, wuctama powes oewsmatow ween LO TECHICAL DOCMElli 74-1126473-00
- The BWST inventory should be carefully monitored when this mode of depressurization is utilised for extended periods of time.
I d. Total loss of feedwater (MFW and EFW) will require a solid water cooldown without the benefit of secondary heat re-moval. At tempt s should be made to obtain feedwater from any available source, however HPI cooling is preferable to
%Ilhe'use "of f non-condensate"igrade ~ feedwater'/ For cases of this type which require excessive cooldown times, BWST inventory should be carefully monitored. HP1 from the BWST will flow into the af facted OTSG and will not be returned to the reactor building sump. Therefore, backup water supplien for the BWST may be necessary and should be prepared. Of fsite releases may be very significant.
I I I I I lO
~
DATE* t@t-82 Appendix C, Page C-31
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 NUCLEAR OPERATIONS TRAINING DEPARTMENT PROGRAM: REPLACEMENT OPERATOR TRAINING COURSE: SYSTEMS TECHNOLOGY LESSON: EMERGENCY FEEDWATER AND EFIC LESSON ITO: ROT-4-15 LESSON LENGTH: 8 HOURS REVISION: 1 ISSUE DATE: 12-3-86 O Prepared By: 7D 9 @jwu clear Instructor i Reviewed and ,4J Concurred With: ' ove#el/M" O Nuclear Training Academic pacialist Approved By: /}$fft s I fuclearTra:,ning Supervisor Reviewed Prior to use: Date Instructor Signature s lO
t blinking. The bypass must be implemented before either OTSG pressure reaches 600 PSIG. This bypass feature bypasses the EFW initiate and the Main Steam and Feedwater Isolation functions. The other bypass that must be implemented is the EPW initiation based on loss of all RCP's. The NI/RPS provides a bypass permissive signal when reactor power decreases below 5 %. The actual bypass function is l performed in the EFIC cabinets by placing the "RCP BYPASS / RESET toggle switch located on the " Initiate" modules in all 4 EFIC cabinets momentarily in the Bypass (Up) position prior to turning off the last RCP. The ' bypass may be verified by observing that the "RCP SHUTDOWN" light on the cabinet alarm panels is blinking. 4.3 Abnormal operations The EFW / EFIC systems were designed to handle the following abnormal events: a) Loss of main feedwater b) Loss of main feedwater with loss of offsite power. c) Loss of main feedwater with loss of offsite and onsite AC power.
- d) Main feedwater line break e) Main steam line break /EFW line break f) Small break LOCA 4.3.1. Loss of Main Feedwater- Upon loss of all main feedwater both EFW pumps are automatically started by the EFIC
, system. A minimum flow of 740 GPM is sufficient to mitigate the effects of a loss of main feedwater event. This allows a single failure on an EFW train to occur and still meet design requirements. After EFW initiation, the l 4 O steam generator level will be automatically controlled at 29
about 24". The only operator actions are to confirm that EFW flow has been initiated and that a level has been established in both OTSG's. 9 4.3.2 Loss of Main Feedwater with Loss of Offsite Power- Upon loss of offsite power (which causes loss of all Main Feedwater pumps and RC pumps), the EFW system will be used to establish natural circulation in the RCS. The turbine driven pump will be started when the system is initiated and ASV-5 and ASV-204 are opened . The motor driven pump (EFP-1) start is delayed until 5 seconds , af ter the diesel generator breaker closes or, if a HPI actuation is present, it is delayed until the block loading sequence is completed and then started with a 5 second time delay. The total time, including the 10 seconds required for the diesel start, from signal to pump start is 30 seconds. While the motor. driven EFW pump is operating and powered from the diesel generator, the load on the generator is monitored and if it exceeds 3000 KW,4an alarm is actuated that informs the operator that the diesel generator is above it's 30 minute rated load. When this happens, a 30 minute timer is also started. If at the end of 25 minutes the load on the diesel has not been reduced below 3000 KW, another alarm will be received that the diesel s generator is at 25 minutes of it's 30 minute rating. If af ter 30 minutes the diesel load has not been reduced below 3000 KW, the motor driven EFW pump will be tripped. 30
-u...._ . . . . . . . .
Rev. 44 11/15/86 A U
- x .g.;e
. m 0-r . .
W P, ..n;o
+ ce f t 1
(i E U g' ',',' g; , ,, m J.>L. . ~ #
,,,s *~ .se*'
~"
t2 OPERATING PROCEDURE OP-204 TLORIDA POWER CORPORATION CL'.'STAL RIVER UNIT 3 POWER OPERATION TEIS PROCEDURE ADORESSES SAFETT RELATED COMPONENTS APPROVED BY: Responsible Section Superintendent / j Supervisor A- Y N m Det /3l//f$ o INTERPRETATION CONTACT: Nuclear Operations Superintendent
o 4.1.1.3 The nazimum rate of power increase below 20t FP shall not exceed 10% per hour. Above 20% FF, Transmission Systes limits shall apply. 4.1.2 T=h-imace n=A onadrant Power Tilt timits. 4.1.2.1 Malatain power imbalance per Nuclear Reactor Specialist's Guidance. 4.1.2.2 If the operator fails to move or moves the axial power shaping rods (APSR's) in the wrong direction, the action could result ,;- in a reactor trip. 4.1.2.3 APSA's shall not be inserted or withdrawn more than an incr'e-ment of 5%, after which power imbalance shall be verified. . 4.1.2.4 To minlaise power tilts, maintain rod position within a group at the same level. . 4.1.2.5 Prior to performing a heat balance, insure quadrant power tilt is ( i 2%. 4.1.2.6 Insure Quadrent Power Tilt is within the limits of S.T.S. l42 3.2.4. l 4.2 REACTOR COOLANT SYSTEM LIMIT $ 4.2.1 There shall be at least three (3) RCP's in operation.
'4.2.2$ ' Reduce reactor power to ( 60% when initiating four (4) to thro'e (3) RCP operation. Assure prior to tripping the RCP'that the Te transaltter is ' selected for the unaffected cold leg; ;For RC pressure control, select the loop with one (1) RCP in the RPS (reactor protective system) per 0F-501, Reactor Non-Nuclear Instrumentation, Section 7.2.
O 07-204 Rev. 44 Page 5
.. - - _- a
~
[ Rev. 34 Effective Date os/23/8s 22 [b 1 Document section NFORM ATION ONL -
, C. R. Nuclear COMPLIANCE PROCEDURE CP-111 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCUMENTING, REPORTING, AND REVIEWING NONCONFORMING OPERATIONS REPORTS O
THIS PROCEDURE ADDRESSES NON-SAFETY RELATE COMPONENTS i APPROVED BY: Responsible Section Superintendent Supervisor vYkA ddLs Date $b t iI ! INTERPRETATION CONTACT: Nuclear Safety & Reliability Supt. e e 6 - - - - , _ _ _ . . _ _ _ _ _ _ _ _ _ _...y. ....
_ . . . . . . _ . . . ~ . . NCOR IMMEDIATE NOTIFICATION REQUIREMENTS ENCLOSURE 4 (Continued) (Page - 7 of 10) C. 10 CFR 20.402 Reports of Theft or Loss of Licensed Material Imediate Notification: CR-3 snall report to the NRC Operations Center via the Emergency Notification System (alternate means - comercial telephone-(202) 951-0550) imediately after CR-3 determines f that a loss or theft of licensed material has occurred in such quantities and under such circumstances that it appears to CR-3 that a i i substantial hazard may result to persons in unrestricted areas. i . i l 0. 10 CFR 20.403 Notifications of Incidents ' i j a. Immediate Notification: CR-3 must imediately report to OHRS (see ! EM-206 for phone numbers) and shall imediately report to the NRC Operations Center via the Emergency Notification System (alternate i .means - comercial telephone (202) 951-0550) any events involving by-product source, of special nuclear material possessed by CR-3 that may I have caused or threatens to cause: l (1) Exposure of the whole body of an individual to 25 rems or more of radiation; exposure of the skin of the whole body of any individual of 150 rems or more of radiation; or exposure of the feet, ankles, hands, or forearms of an individual to 375 rems or more of radiation; or (2) The release of radioactive material in concentrations which, if averaged over a period of 24 hours, would exceed 5000 times the limits specified in 10 CFR 20, Appendix B, Table II; or (3) A loss of one working week or more of the operation of any facilities affected; or CP-111 Rev. Page 31
m- .% . () V NCOR IMMEDIATE NOTIFICATION REQUIREMENTS ENCLOSURE 4 (Continued) (Page 8 of 10) (4) Damage to property in excess of $200,000,
- b. Twenty-Four Hour Notification: 4R-3 must immediately report to OHRS (see EM-206 for phone numbers) and shall within 24 hours of discovery of the event, report to the NRC Operations Center via the Emergency Noti fication System (alternate means - comercial telephone (202) 951-0550) any event involving licensed material possessed by CR-3 that may have caused or threatens to cause:
(1) Exposure of the wnole body of any individual to 5 rems or more of - radiation; exposure of the skin of the whole body of any individual to 30 rems or more of radiation; exposure of the feet, ankles, hands, or forearms to 75 rems or more of radiation; or (2) The release of radioactive material in concentrations which, if averaged over a period of 24 hours, would exceed 500 times tne limits specified for such materials in 10 CFR 20, Appendix B. Table II; or . (3) A loss of one day or more of the operation of any facilities affected; or (4) Damage to property in excess of $2000. E. 10 CFR 50.36 Technical Specifications All reports performed under this requirement shall be made to the NRC Operations Center via the Emergency Notification System (alternate means - c comerical telephone (202) 951-0550).
- a. Safety Limit (STS 2-0): If any safety limit is exceeded, CR-3 shall notify the NRC Operations Center as required by sections A.b.i . (10 CP-111 Rev. $4 Page 32
. :: /
2.1.3 The personnel assigned to shift operations perform three O general functions: U 1. Continuous normal operation of the plant and its associated equipment, including normal planned power changes, startups, and shutdowns.
- 2. Maintain the plant in a safe - condition during abnormal conditions.
- 3. Protect the health and safety of the public, plant personnel, and plant equipment during and following an emergency situation.
l A Senior Reactor Operator (SRO) shall be in the control Center during Modes 1 through 4. All major plant operations are
- conducted from the Control Center with the Nuclear Shift i Supervisor in cosaand. The operating shif t, consistent with j the provisions of P00AM (plant Operating Quality Assurance Manual), effects the Load Dispatcher or other authorized
- O V e orders.
! 2.1.4 Authority to shut down the reactor rests with:
- a. Nuclear Operator
{ ,
- b. Chief Nuclear Operator
{ Assistant Nuclear Shift Supervisor c. i
- d. Nuclear Shift Supervisor
- e. Nuclear Cperations Superintendent
- f. Nuclear Plant Manager or ' Man On-Call' Authority to start up and return to power operation rests with,
- a. Nuclear Operations Superintendent;
- b. Nuclear Plant Manager or ' Man on-Call' 4
i i lO AI-500 Rev. .6$ Page 3 i
*.+.m . .,;u, - c.f . . . . _
~
f*
/O -
} 4.4 An Operator may fill out the Clearance order with a Licensed C Operator' review and concurrence. To indicate concurrence, the Licensed Operator must sign outside the ' Operator Recording order' block. The responsibilities include researching all Clearances and insuring that the number and type of tags issued, and their intended location, is such that the person n classification involved in the clearance can perform the activity without the risk of personnel or equipment safety. This,must be done by first questioning the person n classifi-cation requesting the clearance / Tag to determine the scope of the intended clearance / Tag and then to utilize whatever is necessary to accurately record the clearance. 4.5 The plant Review Connittee (PRC) must review and approve any Clearance, prior to issuance, which meets any condition speci-fled below:
- a. The clearance is to be issued for an unusual. non-reatine, (o _,/ or ahanraal evolution (i.e., repair of RCV-11 in other than Mode 5 or 6, and other energency repairs),
- b. The Clearance to be issued cannot mest the double valve orotection guidelines of 1 500 psig and/or 1 200F, and l57 greater than or nual to 1/2 inch diameter opening.
l57 EXCEPTION: The Clearance Authority say, with approval of the l Man-On-Call, approve clearances which do not meet these guidelines. If the guidelines cannot be met, l57 and approval is given, it shall be annotated in l Iten 5 by writing or stamping in red ink 'Does Not l Meet Double Vale Guideline
- initialed and dated by l the clearance authority. l s
CP-115 Rev. 58 Page 9
;3--- $ . mm. , .
,,, g3. .g. , . - ,
,.,.g.y ,,.,- 47: .. ; 3 . .
.}}