ML20207G402
| ML20207G402 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/22/1986 |
| From: | Hickle B FLORIDA POWER CORP. |
| To: | |
| References | |
| PROC-861222, NUDOCS 8701070288 | |
| Download: ML20207G402 (177) | |
Text
_ $..,,..,.;,Gl.?S,~.;i j'~. li n.--a.c.'qs %,.; -
.i.-~ s.+b.z3. ;
'T'hh.a.?..l ln.' :
e o
(~'s Rev. 10 12/12/86
\\
t O
r Document Cection N FO R M AT 2 O f f C N L W/
C. R. Nuclear EMERGENCY PLAN IMPLEMENTING PROCEDURE EM-307 FLORIDA POWER CORPORATION CRY!'?AL RIVER UNIT 3 SAMPLING AO ANALYSIS OF THE REACTOR COOLANT SYSTEM, THE REACTOR BUILDING SUMP, AND THE MISCELLANEOUS WASTE STORAGE TANK UNDER ACCIDENT CONDITIONS I
O'd THIS PROCEDURE ADDRESSES NON-SAFETY RELATED COMPONENTS REVIEWED BY: Plan. Revie Committee l
/
e 12/12/86 l
Meeting No.
86-49 l
APPROVED BY: Nuclear Plant Manager
~BV $
///71 n
\\
Date
/2 /t t /F0 l
8701070288 861222
/
PDR ADOCK 05000302 F
PDR INTERPRETATION CONTACT: Nuclear Safety Supervisor Adq$
I((
w w
a.;h.Ac.aMywase ega;,tCiC ' '
- .n&hr.;4RNs. ? IY;3.Eb2$h$ *i ';
, ? r.' l$h : ': N;;[j 5.b :'.. p N N N f n ? $ ~ $.
i,
~~~
i
.N I
\\
1 N, /
TABLE OF CONTENTS 2.AEfl Section 1.0 Purpose 1
Section 2.0 General Guidelines 1
Section 3.0 References 2
Section 4.0 Instructions 2
4.1 Sampling RCS At Pressure 3
4.2 Sampling RCS When on Decay Heat or 6
Low Pressure Injection 4.3 Sampling RB Sump 9
4.4 Sampling MWST 11 4.5 Isotopic Analysis 13 4.6 Chemical Analysis 17 4.7 Grab Sampling 29 4.8 Flushing After Sampling RCS At Pressure 32 4.9 Flushing After Sampling RCS When On Decay 35 Reat or Low Pressure Injection 4.10 Flushing After Sampling RB Sump 37 4.11 Flushing After Sampling MWST 38 Section 5.0 Calculations 41 Section 6.0 Notification 41 Section 7.0 Enclosures 41 1
EM-307 Rev. 1 0 page ci)
_eaajia.Wi?ifleipMG M 6m/4jv#f.j W W MfMy,apffE Q W iAG G G d % WF' M 9 9?
[
^
-*.y....,4, dyn Q. -w ~_um sar.. nh, a r -. s.b,V+ "..
- f'W,Ty.fght.
" _..
- _:~ "'
1.0 PMPOSE
,S -
1.1 The purpose of this procedure is to describe the actions taken to sample and analyze the Reactor Coolant System (RCS) under accident conditions for radioisotopes up to C:/ce, dissolved hydrogen con-centrations from 0 to 2000 cc/KG, boren concentrations from 0 to 6000 ppa, sulfate and chloride concentrations from 0.020 to 20.00 ppa (greater concentrations can be measured using appropriate cal-ibration standards), and pH in the range of 1.0 to 14.0.
2.0 GENERAL GUIDELINES 2.1 Performance of all or part of this procedure will be done on the instruction and authority of the Energency Coordinator.
O 2.2 Entry into controlled access areas will be under the direction of the Radiation Energency Team as outlined in EM-208, Duties of the Radiation Emergency Team.
2.3 For the on-line analysis essentially all operations may be con-ducted from the Counting Room, the Primary Laboratory and the Main l9 Control Room, however, monitoring for radiological concerns should be provided.
2.4 An additional requirement of NUREG-0737 is the capability to remove grab samples of the reactor coolant should the in-line system fail or confirmations are requested.
EM-307 Rev1 0 Page 1
Aucq, t Wya%opkguhi:s+Myqh&Z.a@fse. wk.Mu.u.kdia6MD ucu s. 7 - T ~ i.a-
,,. ; u. :.,.,, ';..n - 6 s&l-/. v4., u....> a..,. %&.;.
.i;
.R *
, r:
-n e
drm 2.5 During some post accident sampling, extremely high radiation dose
\\
c I
'~'
levels could be experienced.
The ability to perform all of this procedure will require pre-planning to stay within exposure limits and maintrin doses as low as reasonably achievable.
2.6 As long as this procedure is being used, all samples are returned to the containment sump.
3.0 REFTRFW'EN 3.1 EM-208, Duties of the Radiation Emergency Team 3.2 NUREG 0737 3.3 Drawings FD-302-700.
Enclosures 3 and 4 are for guidelines use only.
3.4 CH-194, Chemical Analysis with the Dionex Ion Chromatograph (N-)
3.5 CH-195, Chemical Analysis with the Digichem 3000 programmable Chemical Analyzer 4.0 INSTRUCTIONS l
NOTE: Enclosure 5 to be utilized by Chemistry supervision to indicate which analyses and reports they want completed.
NOTE: Enclosure 6 to be completed and forwarded to the Emergency Coordinator prior to leaving the General Assembly Area.
d EM-307 Rev.10 page 2
~ :c iv,ypew: yi~Mf%gn%M MiaE=&aX"' ^
M-
'W
- O - ' ~ ~"
n.
" :. _. : a.2~
" lL...... n.6.,+1.? %.,a vo. w s.2 s ' =. :., 5:h. -. w _ -
Im NOTE: Enclosure 7 to be utilized to determine alternate sample U
points if flush times are going to be a limiting factor due to staytime.
NOTE: To minimize setup and sampling times, some sections and steps of this procedure may be performed concurrently. Use the following guideline:
Perform #1, 2, and 3 concurrently;
- 1 IC Setup (Steps 4.6.6.1 to 4.6.6.14)
- 2 Isotopic (Section 4.5)
- 3 Gas Stripping (Steps 4.6.2.1 to 4.6.2.4) and then perform #4 and 5 concurrently;
- 4 H2 (Steps 4.6.5.1 to 4.6.5.3) and pR/ boron (Section d
4.6.7)
- 5 Cl /S01 (Steps 4.6.6.15 to 4.6.6.19) 4.1 SAMPLING THE RCS WHILE STILL AT PRESSURE 4.1.1 Energize or verify the following breakers to activate the listed valves.
4.1.1.1 DPDP5A (124' Control Complex, 480V Switchgear Rm.) Brk. No. 27 for valves CAV-429, CAV-430, CAV-433, and CAV-434.
s EM-307 Rev.1 0 page 3
,... a s. a - u= = ~,w -: -- m w,.. r a m n -. :wnanese>.+ <. w;. c::,'~~v.
- ~ - -
...u..- x.. w.:
r.-*-
e se.^
t i.:
e r'
wN _,,,. e,y. + e ;;e.~ ;
s.: 3:_._ w - ;...+,
+.
in -Y, w.._ _ _ ^ l
_ ;;_ ~
-;. 3.
(h 4.1.1.2 DPDPSB (124' Control Complex, 480V Switchgear Rs. ) Brk. No. 8 for
( )
valves CAV-435, CAV-436 and CAV-432.
'~
NOTE: The following valves are operated from the Counting Room.
4.1.2 Open CAV-519 (ISP Inlet).
4.1.3 Open CAV-447 (Grab Sampler Bypass).
4.1.4 Open CAV-437 (ISP Outlet).
4.1.5 Open CAV-448 (Return to Sump).
4.1.6 Close CAV-439 (Return to MWST).
4.1.7 Verify closed CAV-484 (From IRP).
NOTE: The following containment isolation valves are operated from the Main Control Room.
b NOTE: See Enclosure 1 for alternate valve list.
4.1.8 Open CAV-436 (Return to Sump, Outside Containment Valve).
4.1.9 Open CAV-434 (Return to Sump, Inside Containment Valve).
4.1.10 Open CAV-431 (Sample Supply to PASS, Outside Containment).
4.1.11 Open CAV-126 (Letdown Sample, Supply to PASS, Inside Containment).
NOTE: The following valves / pumps are operated from the Count i
Room.
l i
l l
l l
( p l G l
EM-307 Rev.1 0 page 4
l l
..w mi.uw.cw an.
+.e. w s = ~. s -.
-~w.
~- :::,;.
p.
.c cg...>3
.~,-._a, n%.. v. : - W-
~ -
- .W.
..u_d = -
- a...
=~
e 3m 4.1.12 Start CAP-11.
7 4.1.13 From the IRP in the Count Roon begin to turn the output adjustment knob on the Moore Remote Setpoint Indicator for CAV-484. Continue until a flow of 0.10 to 0.50 GPM is established as indicated by CA-53-FI on the PASS Mimic Panel.
The bargraph on the right hand side of the Moore Remote Setpoint Indicator should indicate 80 to 90 which corresponds to 40 to 45 psig.
N0yE:
If adjusting CAV-484 does not provide desired system flow and pressure, additional fine tuning may be perfo,rmed by adjusting CAV-532 (Manual Phase Separator Inlet Flow Regulator), CAV-533 (Manual ISP Inlet Flow Regulator),
and/or CAV-539 (ISP Phase Separator Back Pressure i
Regulator) umana117 in the PASS Sample Room (Elev. 95' of the Aux. Bldg).
If manual adjustments are required, close CAV-126 or alternate sample valve.
Close CAV-431.
Fully open CAV-484 to allow the system pressure to bleed off as indicated by a zero flow indication on CA-53-FI from the PASS Mimic Panel.
Open DWV-337 and DWV-470 from the PASS Mimic Panel to begin system flush.
Then, with preplanning l
and Health Physics concurrence and
- coverage, make adjustments on CAV-532, CAV-533, and/or CAV-539.
After adjustments close DWV-470, DWW-337, and CAV-484.
Go to 4.1.10 to return to sample routine.
I EM-307 Rev.1 0 Page 5
.,.., g m.
y,
- c. g tyg q:om y,trg g e m a.p p j.w. ws.-1.:-ec y...;, - r2-a-
- s r.d?.t,.,.(.
.,;,a J
n.
13r&YV.u:s5:w.' mrs ):n - -+ - ? %-
~~
~
D"%u:
N.a x_ '
(N 4.1.14 If phase separator high level alarm occurs, tripping CAV-447 (if
\\
bypassing grab sampler), or CAV-445 (if recircing thru grab sampler), close CAV-484 to allow CAP-11 to pump down liquid level in the phase separator.
Before / GPM is indicated on CA-53-FI clear the high level alarm by stroking the effected valve, CAV-447 or CAV-445, and re-establishing flow by opening CAV-484.
4.1.15 After sample flush, and prior to running PASS program, run the program Job Auto. DIS 68 and observe the indications of thermo-couples CA-54-TE-1 (Downstream of Precooler CAHE-8) and CA-51-TE (Downstream of Cooler CAHE-5).
4.1.16 Temperatures of greater than 120*F on CA-54-TE-1 and 100*F on CA-51-TE indicate insufficient cooling.
If these conditions exist, consult Chemistry Supervision for instructions.
4.1.17 Go to Section 4.5.
4.2 MAMpf.TNG THE RCS WRFN ON DEf'iY RFAT OR LOW PRFRSURE INJECTIg[
4.2.1 Energize or verify energized the following breakers:
4.2.1.1 DPDPSA (124' Control Complex, 480V Switchgear Ra.) Brk. No. 27 for CAV-429, CAV-430, CAV-433, and CAV-434.
4.2.1.2 DPDPSB (124' Control Complex, 480V Switchgear Ra.) Brk. No. 8 for CAV-432, CAV-435, and CAV-436.
{
O EM-307 Rev.1 0 Page 6
l f
m,.
..,,.tg.;M:.s+ w n-c4g: =_. ::mpino,.,+.:.agyp-my:q.g++ yuM :::w;;-; :
...y.,...
Gr. wr ;.'.
e-r.-L,.i._u.i % %
. - w... 42.. ]
-~
2%W.
~ grLa_
., - k.; ;_,
.g _., z;,~,
IV NOTE: The following valves are operated from the Count Room.
4.2.2 Open CAV-519 (ISP Inlet).
4.2.3 Open CAV-447 (Grab Sampler Bypass).
4.2.4 Open CAV-437'(ISP Outlet).
4.2.5 Open CAV-448 (Return to RB Sump).
4.2.6 Close CAV-439 (Return to MWST).
NOTE: The following containment isolation valves are operated from the Nain Control Room.
NOTE: See Enclosure 1 for alternate valve list.
4.2 '7 Open CAV-436 (Return to RB Susp, Outside Containment Valve).
4 Y.2.8 Open CAV-434 (Return to RB Susp, Inside Containment Valve).
4 4
NOTE: The following valves /piumps are operated from the Count Room.
4.2.9 Open CAV-440 (Decay Heat Sample).
4.2.10 Open CAV-441 (If on 'A' Decay Heat Loop) or CAV-442 (If on the
'B' Decay Heat Loop).
4.2.11 Start CAP-11.
\\
^
i y
d l
EM-307 Rev,1 0 Page 7
ql,fgfp2KKr::"oy ujz@ n :&s9fe'-+ * ':aN' ~ f? fnninV' -
.Rc = rim 45.
a..a
- 3. w,..
.o
.. a,a,
7.,
.a s.
' 1'
- ' :q.1..l%72, : *c.% s. u' ~ ~.?*r? ':
~b; 'V&~~,. e- * -_s ' - L <
e~ '19,. J T*:
(
Jt.'-j;:,.y;LL;lL
- A 4.2.11.1 If phase separator high level alarm occurs, tripping CAV-447 (if (a) bypassing grab sampler), or CAV-445 (if recircing thru grab sampler), close CAV-440 to allow CAP-11 to pump down liquid level in the phase separator.
Before / GPM is indicated on CA-53-FI clear the high level alarm by stroking the effected valve, CAV-447 or CAV-445, and re-establishing flow by opening CAV-440.
4.2.12 System flow should be 0.1 to 0.5 GPM as indicated by CA-53-FI on the PASS Mimic Panel.
NOTE:
If manual flow adjustments are to be made, close CAV-441 or CAV-442 to isolate sample flow.
Then open Dvv-337, l
CAV-471, and start CAP-8 to begin system flush.
Then with preplanning Tm Health Physics concurrence and coverage, make adjustments in the Pass Sampling Room (Elev. 95' of the Aux. Bldg.) on CAV-532 (Manual Phase Separator Inlet Flow Reg.), CAV-533 (Manual ISP Inlet Flow Reg.), and/or CAV-539 (Back Press.
Reg.
for the Phase Separator).
After adjustments turn off CAP-9, close CAV-471 and DWV-337.
Go to 4.2.10 to return to sample routine.
4.2.13 Go to Section 4.5.
a EM-307 Rev.1 0 page 8
-..e a g x - ~ ~c.w.
c ry.n=~.
2
=; = - -
,g_ :.-
.w.
u i. '
(
o.a...-
- 1.
- d51... f,,, ;%
'm--~-'~-'%~-. n ~ - Q e_ +-2.s%'~,~^*~~:'*
M:
^**'*"t*:**'-'
"**L~
* 'i. r C..
_x r.
a-~-
" ~
s' a
A "i
[^3 s.3 SAMPLING THE REACTOR BUILDING SINEP V
s s
4.3.1 Energize or verify energized the following breakers:
44.3.1.1 DPDPSA (124' Control Complex, 4807 Switchgear Rm.) Brk. No. 27 for CAV-429, CAV-430, CAV-433, and CAV-434.
71 4.3.1.2 DPDPSB (124' control complex,,480V Switchgear Rm.) Brk. No. 8 for CAV-432, CAV-435, and CAVA436.
s NOTE: The following containment isolation valves are operated from the Main contrel Room.
4.3.2 Open CAV-433 (RB Sump Suction, Inside Containment).
4.3.3 Open CAV-435 (RB Sump Suction, Outside Containment).
4.3.4 Open CAV-434 (RB Sump Return, Inside Containment).
V 4.3.5 OpenjCAV-436 (RB Sump Return, Outside Containment).
NOTE: The follvwing valves / pumps are operated from the Count Room.
4.3.6 Open CAV-519 (ISP Inlet).
4.3.7 Open CAV-447 (Grab Sample By-Pass).
4.3.8 Open CAV-448 (Return to RB Sump).
4.3.9 Open CAV-437 (ISP Outlet).
4.3.10 Close CAV-439 (Return to MWST).
(.)
EM-307 Rev.
Page 9
F
.7 f y.'"?? e, a t.93vs afsz.y,tsrein.--wfM.h.o.h, s.-!W.w.-m S*.X.;:W:.f&
e-e92: CL 2:.:.c.>w - ',
r,O
--.w.
-+-
c:..
,s...
w....;.
..- =;- _ n,.._:.+.:
= g.,:. _.
^
,.3 2,[_,., _. y = - '
e
- rN NOTE: Steps 4.3.11 and 4.3.12 are to utilize Demin Water to e
initially cool the RB Sump Sample until flow is i
established. These steps will prevent possible flashing in the CAP-8 suction line.
4.3.11 Open DWV-337 (Demin Water Supply Valve).
4.3.12 Open CAV-521 (Demin Water Inlet to the ISP).
4.3.13 Start CAP-11.
4.3.14 Open CAV-471 to prime CAP-8.
4.3.15 Start Cap-8 (RB Sump recirculation pump).
4.3.16 when sample flow has stabilized on CA-53-FI (approximately 5 minutes), close CAV-471.
4.3.17 If phase separator high level alarm occurs, tripping CAV-447 (if bypassing grab sampler), or CAV-445 (if recircing thru grab g
i U'
sampler), stop CAP-8 and close CAV-519 to allow CAP-11 to pump down liquid level in the phase separator.
Before p GPM is indicated on CA-53-FI clear high level alarm by stroking the effected valve, CAV-447 or CAV-445, and re-establishing flow by opening CAV-519 and re-starting CAP-8.
4.3.18 System flow should be 0.1 to 0.5 GPM as indicate d by CA-53-FI on the PASS Mimic Panel.
\\
EM-307 Rev.1 0 Page 10 Q - ww;, -pe,'.w.s,eew;rgha:an-ji$g.-s
...-c.ast5m c
,,,. A 7 5 "' ' ~
s y
w
.x
.z a.
.r V., ;; ;. -;. -. p..y,-Q
- - c.. W M- $ _.-'s
- e U'hTe*- ' ! -/ f
- 1 ~v.w.
^., * ( Fj
.g,; j,
,g
,[
e s
,.. nF.
r.
(
)
NOTE: If manual flow adjustments are to be made, close CAV-433
/h kJ from the Main control Room to isolate sample flow.
Then open DWV-337 and CAV-471 and start CAP-8 to begin system flush.
Then with preplanning & Health Physics concurrence and coverage, make adjustments in the Pass Sampling Room (Elev. 95' of the Aux. Bldg.) on CAV-532 (Manual Phase Separator Inlet Flow Reg.), CAV-533 (Manual ISP Inlet Flow Reg.),
and/or CAV-539 (Back Press. Reg. for the Phase Separator).
After adjustments close CAV-471 and DWV-337.
Open CAV-433 to establish sample flow.
4.3.19 Once RB Sump flow has been established, close CAV-521 and DWV-337.
4.3.20 Go to Section 4.5.
4.4 EAMPTTNG THE MISC. WASTE STORACE TANK 4.4.1 Request Operations to verify the WDP-6A and/or WDP-6B (MWST Recirc. Pumps) are running.
NOTE: The following valves are operateu from the Count Room.
4.4.2 Open CAV-519 (ISP Inlet).
4.4.3 Open CAV-447 (Grab Sampler By-Pass).
4.4.4 Open CAV-437 (ISP Outlet).
O
,V EM-307 Rev.1 0 Page 11 5,.,7. ~ :-a n.,;
m.>
,ap
, n,wg a..,, pp.,,..
- .y,
o
--;?E:
- ? ',,.!wi p ;L.,,,,_;,u',
,'s is.
~ " T *,L1*?'** * *:=.* '1-W.'.44-.y _
r>
q <;.y +,s:sy,~.12s_w'*tf.s$'TA';
+'
s
=_'.r.
i
/' T 4.4.5 Open CAV-448 (Return to Sump).
\\
4.4.6 Close CAV-439 (Return to MWST).
i NOTE: The following con +ain = nt isolation valves are operated from the Main Control Room.
NOTE: See Enclosure 1 for alternate valve list.
4.4.7 Open CAV-436 (Return to Susp, Outside Containment Valve).
4.4.8 Open CAV-434 (Return to Sump, Inside Containment Valve).
NOTE: The following valves / pumps are operated from the Count Room.
O 4.4.9 Start CAP-11.
4.4.10 Open CAV-444 and CAV-443 (MWST sample).
4.4.10.1 If phase separator high level alara occurs, tripping CAV-447 (if bypassing grab sampler), or CAV-445 (if recircing thru grab sampler), close CAV-443 to allow CAP-11 to pump down liquid level in the phase separator.
Before / GPM is indicated on CA-53-FI clear the high level alarm by stroking the effected valve, CAV-447 or CAV-445, and re-establishing flow by opening CAV-443.
4.4.10 System flow should be 0.1 to 0.5 GPM, as indicated by CA-53-FI on the PASS Mimic Panel.
(
Rev. 1 0 ease 12 EM-307 min:.;
.an9 y.py._7
-m uy,.s i yymyw.y-:.v,.;;, w.:,
_..yc.,..g,4
"'49llm, W.g, ~&.c
.sMqk..:.,,
.,.r :_L.s o,w _ liL,e a.,;fffh x,_;,
,,ar "
[N NOTE: If manual flow adjustments are to be made, close CAV-443 V,
from the Count Room to isolate sample flow.
Tha.n open Duv-337, CAV-471 and start CAP-S to begin system flush.
Then with preph==ing 8.
Health Physics concurrence and coverage, make adjustments in the Pass Sampling Room (Elev. 95' of the Aux Bldg.) on CAV-532 (Manual Phase Separator Inlet Flow Reg.), CAV-533 (fannual ISP Ir.let Flow Reg.),
and/or CAV-539 (Back Press. Reg. for the Phase Separator).
After adjustments turn off CAP-8, close CAV-471 and Dvv-337.
Open CAV-443 to establish sample flow.
4.4.12 Go to Section 4.5.
f%(']
4.5 ISOTOPIC ANALYSIS 4.5.1 If an isotopic and/or H2 analysis is required, continue with this section.
If an isotopic and/or H2 analysis is not required, go to Section 4.6.
NOTE: Prior to continuing with this section insure the following concerns are met:
1.
Detector should have an adequate supply of LN '
2 2.
HV should be correctly applied to the PASS detector and not disabled via the LN2 Monitor.
O V
EM-307 Rev.1 0 page 13
=:w-wexe_qr.s.v.www. > 4+w,we.wx c S,w, m Mcg w
-> A vv--
. IF
m.
6.1
- 6.,_--.._
je.Mi., M E,,
m..-
, R..
Q.
m emessenesseanneensnetenesenesenesessenessessessnessnessemensessten (V)
CAUTION: Never reset the HV using the LN2 Monitor ' Reset" switches.
Always lower the HV bias voltage to 0 volts before resetting the LN2 Monitor.
222222222922222222222222$$$$$$$22222222222222222222222222222222299 3.
' PASS
- printer has an adequate supply of paper and the printer " Select' light is illuminated.
4.
The disc drive ' Ready" light is illuminated.
5.
A daily detector <alibration using the jobstream Auto. CAL 1 should have been performed.
6.
Due to jobstream flow and function, do not attempt to simultaneously perform both liquid and gas sample analysis.
l t
x 4.5.2 Sign on to the ND6685 computer by entering the following:
HEL 1 (CR)
USER 1 <CR)
NOTE:
(CR) is the symbol for carriage return and must follow each input.
l 4.5.3 Start the jobstream as follows:
JOB AUTO. PASS i
r t
i l'
)
EM-307 Rev.1 0 Page 14 L
[.,) iOI;'J-hyfN*i6 KGWA'd.3%JIR/M'Mr'41.r_QaWN,UI^' ' y,'h4M'k - J
- A -+ enL3-7
.y,:.,.
d s
. ~
.... ~
^ s.~ :,. &c.. a,
x.
=.,xn,
- ,e..
- . x.O.
. s.s,. r :, 4g;.:..a..
m;. - -
/3 4.5.4 The computer will prompt:
(
)
1.
REACTOR COOLANT SAMPLE 2.
DECAY HEAT REMOVAL /RB SUMP /MWST 3.
NONE (END THE JOBSTREAM)
Enter "I' or *2" if an Isotopic Analysis is required.
Then go to Step 4.5.5.
Enter '3" if a RCS Dissolved H2 is required.
Then go to Section 4.6.
Enter
'4" if a Demin Flush is required.
Then go to Section 4.8, 4.9, 4.10 or 4.11 depending on sample flow lineup.
4.5.5 The computer will display the parameters from the last Isotopic Analysis performed and prompt:
/*
\\
\\s__/'
DO YOU WANT TO UPDATE PARS (U) OR EXIT (E)?
Enter "U" to update pars.
4.5.6 The computer will reprompt:
DO YOU WANT TO UPDATE PARS (U) OR EXIT (E)?
Enter "U"
to correct any errors.
Enter
'E' to exit.
4.5.7 The computer will automatically perform the analysis and print out a header and peak search on the line printer.
,r8 j
(
)
i v
l EM-307 Rev.1 0 page 15 1
g;;. -W?^7E9h*FNefe/Ms/i"cQis GN%,.stv.4%'aM}'hcp%3%_IOE-YMEhs
,.fgI.J.
- -~
.s
u 2._:.nl ' 4,n,,..*? nn >.,..'; %.'u.,c2lL., u. JWG - :_ez.';$;i.a.,_ e _.j_'_
j
~
1 l
l I
f w 4.5.8 The computer will prompt:
'V SELECT THE DESIRED REPORT TYPE 1.
FLOWING SAMPLE
SUMMARY
REPORT (CMSUMR) 2.
FLOWING SAMPLE MDA REPORT (CMMDA) 3.
FLOWING SAMPLE EBAR REPORT (CMEBAR) 4.
FLOWING SAMPLE IODINE EQUIV REPORT (CMIEQ) 5.
STANDARD GSP SHORT REPORT (GSSRPT) 6.
STANDARD GSP LONG REPORT (GSLRPT) 7.
STANDARD GSP MDA REPORT (GSLLD)
Enter the number corresponding to the desired report type.
NOTE:
If in doubt as to which report to select, contact Chemistry Supervision.
4.5.9 The compute; will print out the requested report and then prompt:
DO YOU WANT ANY ADDITIONAL REPORTS?
1.
YES 2.
NO Enter "1" for yes or "2" for no.
Answering "1" (yes) will restart the jobstream at Step 4.5.8.
Answering "2" (no) will cause the computer to prompt:
(
EM-307 Rev.1 0 page is
- ~ ~
T Q q,gc.uwpy..= m_.3,ps;y49,,w;
.n.+ygg.p.: _,
-_y.,
y r -,
u y
- ?m..e,_.n.,,','i i 6 w.h.'
a, X,., :B&>:?,
5%..-
-+
. n5%:.
..,, ::l ~~".' ""
/ s.
4.5.10 DO YOU WANT TO PERFORM ANY ADDITIONAL ANALYSES?
I
\\
\\
/
'/
1.
YES 2.
NO Answering "1" (yes) will restart the jobstream at Step 4.5.4.
Answering
'2" (no) will cause the computer to prompt:
ALIGN VALVES TO BEGIN DEMIN FLUSH Go to Section 4.6.
4.6 CHEMICAL ANALYSIS 4.6.1 If a chloride, sulfate, boron, pH, or RCS dissolved H2 is required, leave the jobstream at its present status and continue in this section.
If a chemical analysis is not required, proceed to Section 4.7.
O'
(,j 4.6.2 Before performing any chemical and/or RCS dissolved H2 analysis, gas striping flow must be initiated as follows:
4.6.2.1 Open CAV-523 (on PASS Mimic) to start N2 stripping gas flow. Wait 1 minute before continuing.
4.6.2.2 Start CAP-9.
4.6.2.3 Verify gas flow of 0.011 to 0.028 ACFM as indicated by CA-58-FI on l9 the PASS Mimic.
O.
t\\ _/
s EM-307 Rev.1 0 Page 17
~_
.g.
~wz.Avigia m mu.g;p:ap.an wz,,ytq %gs-;u,-s%g ++:av s :y.
-+
-.. ~
.s
U.- rL.
- 1. eu. !.: _,J.J.x
-;,J36.& '..: Me_5
' NF Q;"
. _ _ f;;'"
,m 4.6.2.4 Verify gas analysis of 0.02 to 0.066 ACFM as indicated by CA-60-FI l
\\
before proceeding.
If flow exceeds 0.066 ACFM, secure system flow by:
Closing CAV-126, CAV-003 or CAV-001 if sampling RCS/PZR, or Closing CAV-441 or CAV-442 if sampling decay heat, or Closing CAV-433 if sampling RB Sump, or Closing CAV-443 if sampling MWST.
4.6.3 If a chloride or sulfate analysis is required, go to Step 4.6.6.
If a chloride or sulfate analysis is not required, go to Step 4.6.4.
4.6.4 If a boron or pH analysis is required, CAV-525 and go to Step 4.6.7.
If a boron or pH analysis is not required, go to Step 4.6.5.
4.6.5 If a RCS dissolved H2 analysis is required, go to Step 4.6.5.1.
\\
'w. '
If a RCS dissolved H2 analysis is not required, go to Section 4.7.
4.6.5.1 The computer will prompt:
1.
REACTOR COOLANT SAMPLE 2.
DECAY HEAT REMOVAL /RB SUMP / MISC. WASTE STORAGE TANK 3.
NONE (END OF JOBSTREAM)
Enter
'3".
l I
l
,S
(
v EM-307 Rev. 1 0 page 18 3 '-;
T.Ghcin.nf,, ca g;gijais;. ;w194.w2 RGs w.ggtyn+:.,.
- ,y,g g.y...
.. ~...
U:23:,.~ :..c, u...:.. n,:,.zi.:i we. k,. ~... : rm
.. ipn. r.w _,.
e; ~- 6
__ 3 _-
.. a..
^-
- ,m 4.6.5.2 The computer will prompt:
SELECT THE PROPER HYDROGEN ANALYZER RANGE 1.
0% - 10*. Scale 0% - 100% Scale Enter *1" or
'2" for the proper range setting which is selected at the H2 Control Unit in the Count Room.
The computer will then respond with the range selected and a hydrogen report will be listed on the line printer.
4.6.5.3 The computer will then prompt:
00 YOU WANT ANY ADDITIONAL ANALYSES?
1.
YES 2.
NO Answering *1" (yes) will restart the jobstream at Step 4.5.4.
Answering *2' (no) will cause the computer to prompt:
ALIGN VALVES TO BEGIN DEMIN FLUSH Go to Section 4.7.
/s\\
\\
N._)
4.6.6 chloride and Sulfate 4.6.6.1 Before starting up the Dionex IC check the following:
4.6.6.1.1 IC plugged into 120 VAC.
4.6.6.1.2 Red instrument air tubing secured to air bulkhead.
4.6.6.1.3 Blue eluent tubing secured to analytical pump outlet.
4.6.6.1.4 White eluent delivery tubing secured to the analytical pump inlet bulkhead (#1 position) for sodium tetraborate, (#3 position) for l10 carbonate / bicarbonate.
l NOTE: Eluent #1 is for determination of chloride in a boron l10 matrix - this eluent will not elute sulfates.
l Eluent #3 is for sulfates and other anions.
l f3 N_,
EM-307 Rev.1 0
,,y, 39 M Q % %D%isx+ss%%?nt.% W "'t.R W*^&- 'WiiE?"
E~
~
c'
??.,
- .Y% ^
e 22..
.2hM s.5n.~
. ~~W
' :&-T
. a_. y;; ; _ _._ ;
1
/N 4.6.6.1.5 White desin water delivery tubing secured to the analytical pump
'j
(
inlet bulkhead (#6 position).
4.6.6.1.6 Adequate volumes of eluent, regenerants, desin water, and calibration solution are in their containers.
For reagent preparation see Enclosure 2.
4.6.6.1.7 Thermal conductivity BNC leads are properly connected to the back of the conductivity detector module (Two cell leads and one Thermistor Lead).
4.6.6.2 Depress the POWER button.
Instrument LEDs will light.
4.6.6.3 Verify the following conductivity detector module LEDs are in their correct positions:
4.6.6.3.1 Local / Remote is " Local'.
4.6.6.3.2 CELL is *0N".
4.6.6.3.3 Auto 0FFSET is "0FF'.
O I
4.6.6.3.4 Temperature Compensator is
't.7".
4.6.6.3.5 Scale - the scale setting can be varied depending on the nature of the sample being analyzed. The scale automatically sets itself at 30 when the POWER button is depressed.
If, after obtaining the first printout, there is a peak (s) that is off-scale, increase the scale setting i increment and repeat the analysis. The goal is to have the* scale setting as low as cossible while maintaining all neaka of interest on scale.
4.6.6.4 Verify the following analytical pump module setpoints:
4.6.6.4.1 Local / Remote is " Local".
4.6.6.4.2 Low Pressure Pump trip is 208.
O EM-307 Rev. 1 0
.]
page 20
~
':iMV%y&phiffH'iMmpQQy399.Qu5??? e +':=w;v s -
c-
.,i,
, M:,. _
L%e
- Gu "'.
'i
~
i;...w__
?- :.
" =. -
.._2 w_.
(y 4.6.6.4.3 High Pressure Pump trip to be set at 200 psi above operating l9
)
'd l
pressure.
4.6.6.4.4 Flow rate is 2.0 al/ min.
l 4.6.6.5 Select the eluent solution to be used and depress its col as-ponding selector switch. A red LED lamp shculd light just to the right of the switch.
ELUENT 81 is for chlorides in the presence of borates.
l9 ELUENT 83 is for sulfates and other anions.
l 4.0 6.6 Depress the analytical pump Stop/ Start Switch.
As the pump comes on the LED should move from the stop'to the start position and the pressure indication (located just below the Stop/ Start Switch) should start to increase.
It is not uncommon to have to start the pump 2 or 3 times before it will stay on.
The pump outlet pressure indication will stabilize momentarily and the pump
' Ready' LED will light.
NOTE:
If the system pressure is indicated to be less than 208 the low pressure trip point set in 4.6.6.4.2 will have to be lowered to f until after the pump is started and system pressure has risen to at least 304.
NOTE:
If the pump will not sustain a stable pressure, one or both of the pump cylinders is airlocked. explains the procedure for priming the airlocked pump.
n
- x. s EM-307 Rev.1 0 page 21 g
~b
~g;3.h.::;34;,5;g.ayas;mus. ;;;;9.sig.
g;;;:. u
,.x..s : a
.3
..Lu
';uK,=.-~.
- J u. -.. _.
^
..u_.
,MS 4.6.6.7 At the top of the Advanced Chromatography Module are two sets of
\\'
valve controls labeled System 1 and Systen 2.
Systen 2 is reserved for PASS use.
Verify the following System 2 valve positions:
4.6.6.7.1 Load / Inject is " Load".
4.6.6.7.2 A valve is
- 0N".
4.6.6.7.3 B valve is
'ON".
4.6.6.7.4 Local / Remote is ' Local".
4.6.6.8 Allow the conductivity reading to stabilize before continuing.
It is considered stable when the reading is unchanged (to two decimal places) for 2 minutes.
4.6.6.9 Align the Calibration Solution Select Valve to the ' calibration" position and start the calibration pump (at the reagents cabinet outside the wall of the PASS roca).
7 IL NOTE: The line from the IC calibration pump to the
'B' valve can be flushed at greater than 15% pump stroke if the
'B' valve is switched
'0FF" before the pump. stroke is raised.
Switching the
'B' valve *0FF* diverts the flow to waste allowing rapid line flushing.
Return the pump stroke to between 10% and 15% before returning the 'B' valve to the
'ON' position.
1
\\
EM-307 Rev.1 0
_J Page 22 TlG+%;nA9dgswh4!Qi..f:':.a:!.wkn..
4W '_.% 5. a
- , c.. a <.
- u. -
~"~T
=
. +.
- w,., _
~ct ~ _
"g * -
3._
. _7 5
NOTE: If the pass e4==i e= 1 drainline high level alarm is D
(O activated (as indicated by the alara light located to the left of the calibration pump), the IC calibration pump will not start.
The alarm must be cleared by a reset switch on the PASS panel in the Counting Room.
NOTE: If the calibration pump is not operational, calibration solution any be loaded manually using a syringe with a block coupler in the PASS cahinet in the PASS Room, disconnect the sample inlet line from the load / inject valve and connect the syringe.
Slowly inject
~1 al of ea1iheation solution.
4.6.6.10 Program the HP3390A Integrator by depressing the following keys in order.
4.6.6.10.1 "Zero",
"10',
" Enter" 4.6.6.10.2 'ATT2t *, *10",
" Enter" 4.6.6.10.3 'CHTSP",
'0.5*, ' Enter' 4.6.6.10.4 'PKWD*,
'0.04", " Enter' 4.6.6.10.5 'THRSH',
'9",
" Enter
- 4.6.6.10.6 "ARREJ", '50,000", " Enter' 4.6.6.10.7 'OP(
)*,
'4',
" Enter
- 4.6.6.10.8 'ATT2t',
'8',
' Time",
'5' l9 EM-307 Rev. 1 0 Page 23 w& > kud&h '.
i "~ ~ ~ ~ L
~
yqt;sa;wfhi.bunMf;t5k:;senL gw ~
n M.u.
r ;g.,,
mu -
.a-
-mu.
u-
- x ~.,s :- - z.
r-~
s-r D r<
w Qh,, n
- G'Ma.:u a-
- * - - ~ - - - - -
f-g 4.6.6.11 As soon as the conductivity reading has stabilized the IC is ready
(
)
U for calibration.
Utilize the AUTO OFFSET switch on the Conductivity Detector module to better determine the rate of change in the conductivity reading.
Proceed when the reading has ca=nletelv stabilized.
4.6.6.12 Switch the Auto Offset
'0FF" and
'ON".
Wait 10 seconds.
4.6.6.13 Simi>1hneousiv switch the System 2 Load / Inject valve to the
" Inject' position and depress the integrator " Start" button.
4.6.6.14 After 5 seconds return the Load / Inject valve to the " Load" position.
4.6.6.15 When the chromatographic separation is complete, "Stop" the j ')
i integrator.
Adjust the scale position as needed to place all peaks of interest on scale.
4.6.6.16 After allcwing the conductivity reading to restabilize, repeat V
4.6.6.12 thru 4.6'.6.15 until you get 2 consecutive printouts in which the chloride and sulfate peaks are of equal height (tSt).
4.6.6.17 Form a calibration table in the integrator by depressing the following keys in sequence:
4.6.6.17.1 'CALIB", 'ESTD'.
The integrator will ask for REF'tRTW. Depress 4.6.6.17.2 "10',
" ENTER'.
The integrator will ask for itRTW. Depress i O EM-307 Rev.1 0 page 24 12MQgMc%.7 s igis ' ~
~ ce~- e
- -qD.m
- c-
.T "' ~
V %.'J-'
_. 2.'.
a..k..:._n;.
.,. d %.. w :-L u.__
alD...-
'~~*
/-
4.6.6.17.3 *10',
" ENTER".
I
\\
The integrator will ask for CAI,81 retention time.
Enter the most recent retention time for the chloride peak with the following sequence.
(Example C1 retention 7.03 min.)
l9 4.6.6.17.4 '7.03",
' ENTER".
l Then enter the chloride concentration of the standard.
~ For a 10 ppa standard you would depress:
4.6.6.17.5 *10.0",
' ENTER" If there are no other peaks of interest in the calibration solution depress the ' Enter
- key one more time.
This terminates the calibration table.
The instrument is now calibrated and is ready for sample introduction.
4.6.6.18 Prior to beginning the sample analysis:
4.6.6.18.1 Switch the 'B' valve *0FF".
4.6.6.18.2 Turn '0FF" the calibration solution pump.
4.6.6.18.3 Insure the conductivity reading is stabilized and zerced by cycling the Auto offset '0FF' and 'ON".
4.6.6.18.4 Insure the I,oad/ Inject switch is in ' Loa'd" for at least 1 minute.
4.6.6.18.5 Insure gas striping flow is establ.ished per Step 4.6.2.
4.6.6.18.6 Open CAV-525.
l l
l 1
s 10 page 25 EM-307 Rev.
'J cc:
..%..,f1_. J ~,'~~;.iL' :,7.
Gjisyy h -~.9eEhi,
- v. u-- nyAv:mmeAA
1 G
s_....-.
.. '.. ~.a i. :
)
4.6.6.19 Begin sample analysis by sinti1+=neousiv depressing the integrator
,3
' i.V)
' Start" button and switching the Load / Inject valve to " Inject".
This initiates chromatographic separation of the sample.
Allow the separation at least 10 minutes before stopping the integrator.
The integrator printout will compute the chloride and sulfate concentrations directly.
4.6.6.20 Repeat 4. 6. 6.18 and 4.6.6.18 until 2 consecutive analyses show equal (110%) amounts of anions of interest in the sample.
l9 NOTE:
It may take 2 or 3 sample analysis to completely flush the talibration standards from the system.
4.6.6.21 Upon finishing the sample analysis the column must be rinsed with desin water to prevent carbonate fouling.
To do this, depress Eluent Switch 86 until its LED indicator lights.
Depress Eluent Switch 81, or 3, until its LED indicator goes out.
l9 These 2 steps switch the pump suction from eluent to desin water.
4.6.6.22 When the conductivity reading stabilizes, perform the following to secure the IC:
4.6.6.22.1 A valve '0FF*.
4.6.6.22.2 B valve '0FF'.
i 4.6.6.22.3 Pump Stop/ Start to "Stop" l
4.6.6.22.4 Power '0FF" 4.6.6.23 Go to Step 4.6.4.
N EM-307 Rev. 1 0 page 26 n.a.,.Fav y,.
- ' yL_~l ~
-;sg :u>-
tay;r.:.w.m m;gc=sw.,: J.D
.v.
e
.r-a._m. A
_ A&_ _ _.. _
. 9M.2 1
--n-
_ _ i---
j 4.6.7 Baron and na b
4.6.7.1.
Before use of the Ionics Digichen Boron Analyzer, insure the following:
4.6.7.1.1 Power is *0N' and the instrument key is in " Manual".
4.6.7.1.2 Instrument calibration is up to date.
4.6.7.1.3 Insure adequate volumes of all reagents are in their containers. describes these reagents and methods for their preparation.
~
4.6.7.1.4 Have Chemistry Supervisor select which sequence is to be used.
Sequence 3 is for boron concentration between 200 and 2000 ppm, and Sequence 4 is for boron concentrations greater than 2000 ppm.
4.6.7.1.5 Open Dwv-337.
4.6.7.1.6 Open CAV-525.
O V
4.6.7.2 Depress the " Reset" button.
This requires the computer to perform i
an internal check.
The word ' HOLD
- should appear on the instrument's display until the check is complete.
When the check is complete, the ' HOLD
- will disappear and the standby lamp will light.
NOTICE: If the word ' ERROR
- appears during the internal check, it is. indicative of a
problem with the analyzer's microcomputer.
Notify Chemistry Supervision immediately so that a computer technician may be brought in to repair i
the microcomputer.
l l
OV EM-307 Rev.
10 Page 27
- m w m y.y. w w.m m m.w ar
- e a n sa.a./ %. s w.. w 5 s
~ T
' W.C --
m m
+
.. a...: n x.
e m
IIOTE: If a pH analysis is required, complete 4.6.7.3 and then continue to 4.6.7.4 for boron analysis.
If a pH analysis is not required, go to 4.6.7.4.
4.6.7.3 To initiate a pH analysis depress the following keys in sequence,
'D0 SEQ'; '6'; 'next"; '3*; *next".
This commands the analyzer to perform sequence 6 (pH analysis) three times, the printer will print the results of each analysis.
4.6.7.4 To initiate a Boron analysis depress the following keys in sequence "D0 SEQ';
"3 or 4"; 'next*;
'3*
'next".
This commands the analyzer to perform sequence 3 or sequence 4 (midrange boron or high range boron) three times.
The printer will print the results of each analysis.
4.6.7.5 When all pH/ Boron analyses are complete the sample burette and the C) spin cell must be cleaned.
Sequence 10 is designed for this purpose.
Depress the following keys in sequence, 'DO SEQ'; *10*;
'next*;
'1';
'next'.
This commands the analyzer to acid wash the spin cell and to rinse the sample burette with demineralized water.
4.6.7.6 Close DWV-337.
4.6.7.7 Go to Step 4.6.5.
C']-
\\m EM-307 Rev.1 0 Page 28
--i L
.1 TT~
,.3 nsniph '.1.% 'N MceWi ' ? 'inr :6m :
- :.sW ~ :
z.a; q ;;is
..=,q_,_
yu,.
Jm 4.7 GRAB SAMPLING (V
NOTE: Preplanning is required to address radiological concerns and Realth Physics coverage should be supplied prior to continuing with this procedure.
Health Physics must be consulted for entry into the Aux. Building.
4.7.1 If the required lineup is not established for the sample point of interest, go to Sections 4.1, 4.2, 4.3 or 4.4.
Then continue to 4.7.2.
If the required lineup is established for the sample point of interest, go to Step 4.7.2.
If a grab sample is not required, go to Sections 4.8, 4.9, 4.10, or 4.11 depending on sample flow lineup.
I\\.
4.7.2 Prior to Grab Cm=alinat t
l 4.7.2.1 Insure engagement of cart by unlocking the cart from the station and moving the engagement lever back and forth.
If properly engaged, the cart will also move back and forth. Re-lock the cart to the station.
4.7.2.2 Check the 3-way valves in the open (counter-clockwise) position (Grab Sampler Inlet and Outlet Valves).
4.7.2.3 Turn on the Grab Sampler exhaust fan.
The switch is located to j
the right of the Intermediate Building door (across from RM-A7).
4.7.2.4 Install the Grab Sampler ramp.
EM-307 Rev. 1 0 page 29 2 T;gy4y?Mn:nya %;;E:;;&[swNy.sfcf--e '} }i[: '
y, u., ~"[~ L ;y = _, -
W.s;-
v:x
~w
- e_
w 4.7.2.5 Insure the transit cover and a 3/4" wrench are available.
. e/
\\
4.7.3 From the PASS Mimic Panel in the Counting Room, open CAV-445 and CAV-446 and close CAV-447.
This lineup puts sample flow through the grab sampler.
4.7.4 Allow 5 to 15 minutes for sample to purge through the sampler.
4.7.5 Using the T-handle, turn the Grab Sampler three-way valves fully clockwise to isolate the sample in the sample bomb and direct all the sample flow through the internal bypass line.
4.7.6 Switch the sample lineup to the desin flush lineup per Sections 4.8, 4.9, 4.10 or 4.11 depending on sample flow lineup.
4.7.7 To remove the Grab Sampler, disconnect the Grab Sampler from the sample station by squeezing the disengagement lever and by pushing the engagement handle to its rearaost position.
4.7.8 Pull up on the handle of the cart locking mechanism to release the O
'V cart.
4.7.9, Remove the Grab Sampler and cart to the Turbine Building crane well and install the transit cover over the quick-connects.
The grab sampler can be removed from the cart using the 3/4" wrench and transported off-site.
4.7.10 To install a new Grab Sampler, bolt the Grab Sampler onto the cart and remove the transit cover.
4.7.11 Using the T-handle, position the Grab Sampler 3-way valves to the fully counter-clockwise position for sampling.
1 O
EM-307 Rev.10 pege 30 dQ; Op.4@%.RWG)'er%%ft{.. AMS]%if'4 QU['
-e f
-~
~
~~n,.-
~^
, u..
-w
~~
s.
- c. ~ :..
l
[~N 4.7.12 With one person guiding the sampler assembly, another person
\\
)
should push it up the ramp and onto the platform, halting several inches from the connection points.
enesessessensenessessssseessnesessesseneseassessamensnesessneensse CAUTION: When ca===c+ina the s==aler, force should NEVER be used.
Damage to the quick-connects will result from forcing the connection.
esenesessnesenses
............senes...............................
4.7.13 very carefully, slowly push the sampler into the sample station.
If positioned correctly, the front of the sampler will make metal-to-metal contact with the curved face of the sample station.
4.7.14 If the sampler does not position correctly, pull the eart back a o(V I
short distance and realign it.
4.7.15 Repeat Step 4.17.13 to position sampler. Repeated attempts may be necessary for proper alignment.
4.7.16 Lock the cart to the s,tation by pushing the handle of the locking mechanism completely down, driving the lock-bolt through the hole in the cart.
4.7.17 Gently pull the engagement lever forward until a distinct " click" is heard (the lever must 11Q1 be forced).
This signifies that the quick-connects have engaged.
NOTE: Due to environmental conditions, the click may not be heard.
/^N
\\v)
EM-307 Rev. 1 0 pege 3,
'u~
~ Ti~.l '
2LD, aur. T:y augh:
mf,di.A(
ma.{ka
% uw w ~
.C.:
c..
sw...=_.._.~.:._
r:m, e
4.7.18 To insure engagement, unlock the cart from the station and move 5
x' the engagement lever back and forth.
If properly engaged, the cart will also move back and forth.
4.7.19 Re-lock the cart to the station.
The Grab Sampler is now ready for use.
4.8 FLUSHING AFTER SAMPLING RCS AT PRESSURE NOTE: The following valves are operated from the Main Control Roca.
4.8.1 Close inside containment isolation valve CAV-126 or alternate valve.
,O( )
NOTE: The following valve is operated from the Count Room.
4.8.2 Allow system pressure to bleed off as low as possible as indicated on CA-53-FI on the PASS Mimic Panel.
CAV-484 may be adjusted to facilitate bleed off rate.
A "Zero" flow rate may not be achievable due to the nitrogen stripping flow.
NOTE: The following valve is operated from the Main Control Room.
4.8.3 Close CAV-431.
O iO, EM-307 Rev.1 0 page 32
- . - (;y,;d~f7:7 5 7~0K a2m m'>'
"~GQ.. -
.r..
7,.
~ ~ 7_.a._
u.
.-:-. 2: -
4.
- - ~.
-../
p 4.7.18 To insure engagement, unlock the cart from the station and move
,m (v) the engagement lever back and forth.
If properly engaged, the cart will also move back and forth.
4.7.19 Re-lock the cart to the station.
The Grab Sampler is now ready for use.
4.8 FLUSHIE AFTER SAMPLING RCS AT PRESSURE NOTE: The folloaing valves are operated from the Main Control Room.
4.8.1 Close inside containment isolation valve CAV-126 or alternate valve.
f NOTE: The following valve is operated from the Count Room.
4.8.2 Allow systes pressure to bleed off as low as possible as indicated on CA-53-FI on the PASS Mimic Panel., CAV-484 may be, adjusted to facilitate bleed off rate.
A "Zero" flow rate may not be achievable due to the nitrogen stripping flow.
NOTE: The following valve is operated from the Main Control Room.
4.8.3 Close CAV-431.
10 EM-307 Rev.
Page 32 hw.w.;.+c N
.,P
. mAvem- -
- e. m T.
- p..
T " ~:T
. ;i.~.-- - '
1-
[
2.
.+
_a-
.1 e
m__
_m
..w
-n
. s -J v.ns t
1 NOTE: The following valves
- e operated from the Count Room.
t x,)
4.8.4 Close CAV-484.
4.8.5 Open DWV-337.
4.8.6 Open CAV-470.
4.8.7 Adjust system flush rate utilizing CAV-484.
Do not exceed 0.35 GPM on CA-53-FI on the PASS Mimic Panel.
NOTE: If excessive demin water flow causes high level cutoff trip on the ISP drain, reduce flow rate with CAV-484, close CAV-525, and then press the reset button on the PASS Mimic Panel.
This reset will restore power to the boron analyzer.
O V
4.8.8 Allow the water to flush 10 minutes.
4.8.9 Acquire a manual spectrum.
If a high count rate is indicated, continue flushing.
If a low stable count rate is indicated, answer the computer prompt:
ARE YOU FINISHED FLUSHING?
With
'1' (yes).
4.8.10 Sign off the ND6685 by entering:
' BYE 1' O()
10 EM-307 Rev.
Page 33
- ~ -
m.
-, 7, w.= a, - --
-g
-a-;
-='~=m*-
.m.
w_. -
o.
,2.
_.m..fo
- ex.
w w _..
/
}
')
NOTE: The following valves / pumps are operated from the Count Room.
4.8.11 If Grab Sampling was performed, open CAV-447, 4.8.12 If Grab Sampling was performed, close CAV-445 and CAV-446, and continue flush for 5 minutes.
4.8.13 If chemical analysis was performed, turn off CAP-9.
4.8.14
,If chemical analysis was performed, close CAV-523.
I 4.8.15 Close CAV-470.
4.8.16 Turn off CAP-11.
4.8.17 Close DWV-337.
4.8.18 Close CAV-519.
4.8.19 Close CAV-447.
4.8.20 Close CAV-437.
n)
's 4.8.21 close CAV-484.
s 4.8.22 Close CAV-525.
4.8.23 Close CAV-448.
4.8.24 Open CAV-439.
NOTE: The following valves are operated from the Main control Room.
4.8.25 Close CAV-436.
4.8.26 Close CAV-434, 4.8.27 If Grab Sampling was performed, go to Step 4.7.7.
(
EM-307 Rev. 1 0 p,,,
34 l
l
/
s' A *k NM
- V h
' 88+ b e d *
'd
~
d (k. * ^
^**
a a _ ;.
- :x:
- a.
- s. :
~.:. :
..,,,;,. <:...:.x ::
- s. _ m..
.:n.
..;w ;a.a. _ _..
.,....a...:....
--_ s-4.3 FLUSHING AFTER SAMPLING RCS WHEN ON DEC1Y HEAT OR Ng LOW PRESSURE INJECTION NOTE: The following valves / peps are operated from the Count Room.
4.9.1 Close CAV-441 or CAV-442.
4.9.2 Allow system pressure to bleed off as low as possible as indicated on CA-53-FI on the PASS Mimic Panel.
A "Zero' flow rate may not be achievable due to nitrogen stripping flow.
4.9.3 oren DWV-337.
4.9.4 open CAV-471.
4.9.5 Start CAP-8.
4.9.6
' Allow the water to flush for 10 minutes.
4.9.7 Acquire a manual spectrum.
If a high count rate is indicated, continue flushing.
If a low stable count rate is indicated, answer the computer prompt:
ARE YOU FINISHED FLUSHING?
With "I' (yes).
4.9.8 Sign off the ND6685 by entering:
' BYE 1' NOTE: The following valves / pumps are operated from the Count Room.
O IM 107 Rev.1 0 Page 35
- - ~ ~ ~ ~ "
~ -- " v ^^
~:,..
R
-r
-- u n:
,.u.,
- s.. _
m...
- u.
. m,..
.. a.
.u.a., _.:_.-- -
_~,c-.~..~.
..,.:- _ - =
m.
_..w
.w.=.-:..-.-
r, t
s Ym 4.9.9 If Grab Sampling was performed, open CAV-447.
f 'j '
. a(
4.9.10 If Grab Sampling was performed, close CAV-445 and CAV-446, and a
O.
continue flush for 5 minutes.
4.9.11 If chemical analysis was performed, turn off CAP-9.
t 4.9.12 If chemical analysis was perforted, close CAV-523.
4.9.13 Close CAV-471.
4.9.14 Turn off CAP-11.
4.9.15 Turn off CAP-8.
4.9.16 Close Dwv-337.
4.9.17 Close CAV-519.
4.9.18 Close CAV-447, 4.9.19 Close CAV-437.
4.9.20 Close CAV-525.
4.3.21 Close CAV-448.
f\\
Cl 4.9.22 Open CAV-439.
NOTE: The following valves are operated from the Main Control Room.
i r
3 4.9.23 Close CAV-436.
4.9.24 Closc CAV-434.
4.9.25 If Grat Sampling was performed, go to Step 4.7.7.
I l
EM-307 Rev.1 0 Page 36 s
,,o, -
?, ; f",
,,,,y :s.,
_ d.- _
4>., [.Y
~
jf ',...
" l ~. Ll.?... _ 1 2, _ _,.
. _..1
..'.l$u._ z
I NOTE: The following valves are operated from the Main Control Room.
I 4.10.1 Close CAV-433 and CAV-435.
4.10.2 Allow system pressure to bleed off as low as possible as indicated on CA-53-FI on the PASS Mimic Panel.
A 'Zero" flow rate may not be achievable due to nitrogen stripping flow.
NOTE: The following valves are operated from the Count Room.
4.10.3 Open DWV-337.
4.10.4 open CAV-471.
4.10.5 Allow water to flush 10 minutes.
4.10.6 Acquire a manual spectrum.
If a high count rate is indicated, continue flushing.
If a low stable count rate is indicated, answer the computer prompt:
ARE YOU FINISHED FLUSHING?
With
'1' (yes).
l 4.10.7 Sign off the ND6685 by entering:
I l
' BYE 1*
l
%)
EM-307 Rev.1 0 Page 37 l
, sm.:
gs9n-
- 1s-
,_ -- y--
ll ? > '
- n c'
.. ~...2
=~
NOTE: The following valves / pumps are operated from the Count Room.
4.10.8 If Grab Sampling was performed, open CAV-447.
4.10.9 If Grab Sampling was performed, close CAV-445 and CAV-446, and continue flush for 5 minutes.
4.10.10 If chemical analysis was performed, turn off CAP-9.
4.10.11 If chemical analysis was performed, close CAV-523.
4.10.12 Close CAV-471.
4.10.13 Turn off CAP-11.
4.10.14 Turn off CAP-8.
~
4.10.15 Close DWV-337.
4.10.16 Close CAV-519.
4.10.17 Close CAV-447.
'O 4.10.18 close CAV-437.
4.10.19 Close CAV-448.
4.10.20 Open CAV-439.
NOTE: The following valves are operated from the Main Control Room.
4.10.21 Close CAV-436.
4.10.22 Close CAV-434.
4.10.23 If Grab Sampling was performed, go to Step 4.7.7.
O EM-307 Rev.10 j
page as
,. ' l?=~' ?.
. ?? ';
~'
M T'%,
?:,f
.l*'~"..
a/
',.*iN l
.w.,
=p nz,s
. u _,1
' s. _, :-
a 1
n ' h - i.*.: ~ -
.w=*'
r*u_
- nn'.
4.11 FLUSEING AFTER SAMPLING THE MST NOTE: The following valves / pumps are operated from the Count Room.
4.11.1 Close CAV-443 and CAV-444.
4.11.2 Allow systes pressure to bleed off as low as possible as indicated on CA-53-FI on the PASS Mimic Panel.
A "Zero" flow rate may not be achievable due to nitrogen stripping flow.
4.11.3 open Dwv-337 4.11.4 Open CAV-471.
4.11.5 Start CAP-8.
4.11.6 Allow the water to flush for 10 minutes.
4.11.7 Acquire a manual spectrum.
If a high count rate is indicated, continue flushing.
If a low stable count rate is indicated, answer the computer prompt:
ARE YOU FINISHED FLUSHING?
With *1" (yes).
4.11.8 Sign off the ND6685 by entering:
- BYE 1' NOTE: The following valves / pumps are operated from the Count Room.
v EM-307 Rev.1 0 Page 39
~.
- dt t & -
5 ~~
2 ;u&-
4.,
ca.
..m._._..
.
- __ s
=.
3 g
'4 11 9 If Grab Sampling was performed, open CAV-447.
4.11.10 If Grab Sampling was performed, close CAV-445 and CAV-446, and continue flush for 5 minutes.
4.11.11 If chemical analysis was performed, turn off CAP-9.
4.11.12 If chemical analysis was performed, close CAV-523.
4.11.13 Close CAV-471.
4.11.14 Turn off CAP-11.
4.11.15 Turn off CAP-8.
4.11.16 Close DWV-337.
4.11.17 Close CAV-519.
4.11.18 Close CAV-447.
4.11.19 Close CAV-437.
4.11.20 Close CAV-448.
4.11.21 open CAV-439.
es NOTE: The following valves are operated from the Main Control Room.
4.11.22 Close CAV-436.
4.11.23 Close CAV-434.
4.11.24 If Grab Sampling was performed, go to Step 4.7.7.
O EM-307 Rev.1 0 Page 40 l
l I
t_.,. q.s w.7; _
s-m 7 gep_ _
-7m
.Af
?.
~~ ~~~~~
,.., _ _. ~..
e 5.0 f*17.curlTIONS s
?
)
'wJ 5.1 None 6.0 NOTIFICATIONS 6.1 All data accumulated per this procedure is to be summarized on and forwarded to the Emergency Coordinator via Chemistry Supervision.
6.2 All personnel leaving the general assembly area for the purpose of sampling the Reactor Coolant System per this procedure are to be listed on Enclosure 6 which is to be forwarded to the Emergency Coordinator.
If^x (d
)
N.
7.0 ENCLOSURES 7.1 Enclosure No. 1, Alternate Containment Isolation Sample Valves 7.2 Enclosure No. 2, Reagents for Ion Chromatograph and Baron Analyzer 7.3 Enclosure No. 3, High Pressure AIMS and Chemical Analysis 7.4 Enclosure No. 4, Low Pressure AIMS 7.5 Enclosure No. 5, P.A.S.S. Data Sheet 7.6 Enclosure No. 6, P.A.S.S. and Analysis of RC, Emergency Coordinator Notification 7.7 r.nclosure No. 7, Recommended Sample Flush Times 7.8 Enclosure No. 8, Priming Airlocked Pump A
(Y' EM-307 Rev.
Page 41
,, a_;m -
._g;
. =. _
wg;
- p.w.,
'~ :;.~"~ ~
.a.-
~
- ~.
e
? ~~'
ENCLOSURE 1 i
'~~~'
ALTERNATE CONTAINMENT ISOLATION SAMPLE VALVES.
Samole Alternate Valves CAV-434 CAV-433 CAV-436 CAV-435
' Note a crosstie valve CAV-500 (Intermediate Bldg. Elev. 95' must be opened to utilize this crosstie.
CAV-431 CAV-432 CAV-429 RCP 1A Disch.
V) CAV-126 CAV-430 RCP 1C Disch.
CAV-126 CAV-001 PZR STM Space CAV-003 PZR Water Space p) tV EM-307 Rev.1 0 Page 42 M5a
-pgre:=
="m
-e.:
ua:-- --
~%s.~. y
- 7;~ L,.
...:, asa :g= -
r
-=
_m, -. a.
.. w n
m ION CHROMAT0 GRAPH REAGENTS ENCLOSURE 2 1.
0.25 M dodecylbenzene sulfonic acid (DDBSA), Molecular weight 326.06g.
Dissolve 81.51/p grams of DDBSA (where p is it purity of DDBSA) in 800ml of reagent grade water.
Very gently heat solution while stirring until DDBSA Is completely dissolved. Dilute to 1 liter with reagent grade water.
0.025 N sulfuric acid (H SO ) Molecular weight 98.06g.
2.
2 4 Pipet 200ul of concentrated H SO, into 500ml reagent grade water and dilute to 2 4 1 liter.
CO )/0.075 M sodium bicarbonate (NaHCO ) Eluant l9 3.
O.22 M sodium carbonate (Na2 3
3 Concentrate - Dissolve 6.30 g NaHCO3 and 23.3 g Na2CO3 in ~800 al reagent grade l
water and dilute to the mark in a 1 liter volumetric flask.
l 4.
0.0022 M sodium carbonate (Na2HCO )/0.00075 M sodium bicarbonate (NaHCO )
l 3
3 Eluant - Pipet 10 al of 0.22 M Na2CO /0.075 M NaHCO3 eluant concentrate into a l
3 1 liter volumetric flask and dilute to the mark with reagent grade water.
l S.
_0.005 M sodium tetraborate (Na2 4 7 10 H O) Eluant - For each liter of eluant l
B0 2
to be prepared ' dissolve 1.91 grams Na2 4 7 10 H O in ~500 al reagent grade l
B0 2
water and dilute to the mark in a 1 liter volumetric flask.
l 6.
Chloride calibration solutions - prepare by accurately diluting commercially l
available 100 ppa C1 standard solution into desired concentrations.
BORON ANALYZER REAGENTS 1.
0.1 N hydrochloric acid (HC1)
Add 8.6al concentrt.ted HC1 to 500a1 reagent grade water and dilute to 1000ml.
2.
0.5 M mannitol Molecular weight 182.189 Dissolve 91.099 of reagent grade mannitol in approx. 500ml reagent grade water (use heat as necessary). Dilute to 1000ml.
3.
0.1 N sodium hydroxide (NaOH)
This reagent is commercially available and should be directly purchased or be prepared by direct dilution of a commercially prepared NaOH solution of greater normality.
4.
1000 ppa Boron Standard-i This reagent is commercially available and should be directly purchased.
EM-307 Rev.1 0 Page 43 5~-d" ? -
hik _
D l1F% ~
' NM ^ ,
Cy,
~
~ ~ - -
. _-~ _..... n.m.,.,.
, ~,
c_
v4 e
b ION CHROMAT0 GRAPH REAGENTS ENCLOSURE 2 V
1.
0.25 M dodecy1 benzene sulfonic acid (DDBSA), Molecular weight 326.06g.
Dissolve 81.51/p grams of DDBSA (where p is t purity of DDBSA) in 800ml of reagent grade water.
Very gently heat solution while stirring until DDBSA Is completely dissolved. Dilute to 1 liter with reagent grade water.
2.
0.025 N sulfuric acid (H SO ) Molecular weight 98.06g.
2 4 Pipet 700ul of concentrated H SO, into 500ml reagent grade water and dilute to l10 2 4 1 liter.
3.
Eluent 83 stock solution
[0.22 M sodium carbonate (Na2CO )/0.075 M sodium l10 3
bicarbonate (NaHCO )] Dissolve 6.30 g NaHCO3 and 23.3 g Na2CO3 in ~ 800 ml l
3 reagent grade water and dilute to the mark in a 1 liter volumetric flask.
4.
Eluent #3 - [0.0022 M sodium carbonate (Na2HCO )/0.00075 M sodium bicarbonate
[10 3
(NaHCO )] Pipet 10 al of 0.22 M Na2CO /0.075 M NaHCO3 eluent concentrate into a l
3 3
1 liter volumetric flask and dilute to the mark with reagent grade water.
5.
Eluent #1 - [0.005 M sodium tetraborate (Na2 4 7 10 H O)] For each liter of l10 80 2
V eluent to be prepared dissolve 80' 2
1.91 grams Na2 4 7 10 H O in ~ 500 ml reagent grade water and dilute to the mark in a 1 liter volumetric flask.
6.
Calibration Standards (F, Cl, 50 -2, etc.).
All standards should be prepared l10 4
from commercially available aqueous stock solutions or from the sodium / salts of l
the anions of interest. Some common stock solutions are prepared as follows:
l Chloride - 0.165 g Nacl diluted to If is 100 ppm Cl.
l Fluoride - 0.221 g NaF diluted to 14 is 100 ppa F.
l Sulfate - 0.148 g Na2SO4 diluted to 14 is 100 ppa SO -2, l
4 NOTE: Chloride & Fluoride standards should be prepared in glassware cleared in l10 nitric acid and rinsed thoroughly in reagent grade water.
l NOTE:
If a borated sample is to be analyzed, it will be necessary to spike the l10 standard to an approximate boron concentration expected in the sample to l
match ion retention times due to borate interferences.
l EM-307 Rev.10 Page 43 (Continued on Page 43a)
'>- -m
-~~ 3 r ~ ~
=~---y----
m.
~ ~;g 5c,---
v.y
. ?.-
. a..
. =. ;.w.
~-
~m
- _a...
s
_m
.m__
BORON ANALYZER REAGENTS O
1.
0.1 N hydrochloric acid (HC1)
Add 8.6ml concentrated HC1 to 500ml reagent grade water and dilute to 1000ml.
2.
0.5 M mannitol Molecular weight 182.18g.
Dissolve 91.099 of reagent grade mannitol in approx. 500ml reagent grade water (use heat as necessary). Dilute to 1000ml.
3.
0.1 N sodium hydroxide (NaOH)
This reagent is commercially available and should be directly purchased or be prepared by direct dilution of a commercially prepared NaOH solution of greater normality.
4.
1000 ppa Boron Standard This reagent is commercially available and should be directly purchased.
~
U EM-307 Rev.1 0 Page 43a
. ~ -
n +tgip g w,
- -(
};(
q.,
2T' ~
qq:--
.l.
tg n
(
y
,m c
A linen rtentat A..n', un d Clif e4i( AL
- Vy (j
{
N sticit PRES 50RL Alr45 g,:
MAttiroLO JL CA 54 H(an Lint,
. i
- >4 - CAV-2.
TE-l l'Paz.ssomt COoLt%
EfLetF 70 MIT
{
PR1400L88 EH 6
547
~
W M C R-Q.C O
temenE4 ->
>1 H
>4
><1 D4 DHN n
'd CAV-824 C Ave %38 C Af.es&f CA1 451 M83 CES
{I M C. R.
H C R.
M.
M-gang,.g M*
l '. S. N.
y p -.- H y os
.e es.o i
e.c.e iA J
sai v M*
/k Disannet.t_) _ H 4
C AV"90 Mt R.
g3g M C R-4 C, A-C h.
e
.i
'E E f R4.R IC 549 r
SoCTton
->4-H S'il c.a. )
'. f p
g j:,
ty CAV.430
-+'
N j
h l x,,
M C R-DE Mwt MtO t.J.af.
t ga r.-
a,.
no s
o
.. s, u. _>_ s e.
q-
..., s....
,goe,
~-
CA,.co, TT r iiss fr4(
i Kj'j-
)[***
~
?
,rns p, g, C R. JL'***
D,;,
)
r 4*-
g tw.so Twv.e L
go sta a rat Sf
/,
-1 SitA>4 spnct pq y>, >4 Nb4 D4 1.'r C AV-DOI gse qq y.
f ;<
H C.a.
5,a.
w ca.sa c *-
r
- G P.s.R.
nr.
VAWE OPERMOpt K(y m.
g 6
- t. c.R - Count Roo 4 517 sia 2.. M.C.R - Haus Co.4Taon, Rs.
>4->4-> pt.Artv t an.
c 4.
^,
L id. - unnoAt.
cutoe oc g --- r2& M.
Sir c.a.
CAP.8%
g,g sss
- 9. p,gg. fRMtAR Y sore ><
I'3 IL*'
"NA'T3fE N
kN
(,
j CAP.so gx gg 33 Pg N
4 gn us 7 5'
- i w
u
~.h d
?'*L g A CA-$s Fi
- ,.Y o
Vl 5=
g 0
{.'
h 3I If38 M.
A EZ 7 M./
~
P t-dt 7
14 gy CL 6 h
M-qyy
,P h 4 L'-~
()
jg
-A C.C. JL W39 C 4.
-/*
70 g,j g
qg
~
w
'NMg7 To Mw45T
- f.,
,r 196 c t.
F RO.4 R.S.
JL 7
. ~.N,- bk-k IO C _.S. SON,P o
k
~
,m m.
c M-H C.R.
M C.4.
M.
I
' b
!j
[]
/~l'
?.' };
F LOW PR35$dE AnM3 e
't 2
9 M
74 M
4 K02 434 436 413 443 8
M Mck' MCA M
C R.
1 r 00 d
a FROD4 J b M E O NNP
?I Od 74
?4 5-4 p*
[
g t
7 471 431 435' 41r 417 4
'f ChHE-7 M
McR Mct n
1-M i
CAP-a 1r411 c et s
.2 M
JLCL o
1v
\\./
v 1-J a '.,
470 t-To R.S.
cg
-4 SUMP ti
.g, J L A
m sN m
~
m 1r DWW-H7 441 ]
ft 4 '
]{ PYstARE RELIEF 444 1r O
dM.' 4
/d CK d6 4s+
ss
('
CR FROH DEHid 3p4go dk H160 SuPPt.Y agM v
Faced Mway a
...J
.d.
+ <.
VAWE OPSRATOR WEY
[{L 1:,1
- i. cR-coowy acc+-
ro wocLaxR
- 2. MCA-MAh4 c. cuba _
. E SAMPLE RD0M Roon ag
),b SACE PAtssuer FRoHDuc-3A >
>4 1 r387
,a
[
- 3. M - M Aut.)AL d '
VAWE 44 4, pgg pgggggy Q' ' '3 N 6 AMPLE a, [
FACH CHILLED
!?
RDOM M10 50PPLY C R, FROH DHC-36 >
N p,'
o
,7 441 m
C 556 NEAR LING to i r CA 2
P 3
s 48b I4 NM'4 d '
549 84& K41 of46 u
g C
~
CR M M CR 54
?4 m 2 m2
" ' fg 4 586 487
[
M FAR LtHE ChnL-L M
M L-Low PRESSORE AIMS HAHIFOLO
.t
. I.
'I 4
. -_.a c_r..
.~-
u :..:- - - _ --. ------
.~.
,I^x EM-307 ENCLOSURE 5 I
\\
~
P.A.S.S. DATA SHEET DATE:
TIME:
AIMS ANALYSIS Sampje point:
Flowing Sample MDA Report (CMMDA)
Flowing Sample EBAR Report (CMEBAR)
Flowing Sample Iodine Equivalent (CMIEQ)
Standard GSP Short Report (GSSRPT)
Standard GSP Long Report (GSLRPT)
Standard GSP MDA Report (GSLLD)
(s V)
Total Activity (uCi/cc) from report above, if applicable Major Contributing Isotopes from report, if applicable:
uCi/ce, uCi/ce, uCi/ce, uCi/cc uCi/ce, uCi/ce, uCi/ce, uCi/cc uCi/cc, uCi/ce, uCi/ce, uCi/cc Chemistry Analysis O
Baron opm pH Chloride opm Hydrogen 1 or CC/kg Total Gas CC/kg O
O O
SIGNATURE / TITLE r~
i l
EM-307 Rev.1 0 Page 46 t
- v ge+
.=;.,..
..:-,-r----
_ ::+c
-u.
"=y:.
'~
\\
w.
./r-
-~ ;
1, + w * * " s _ h _. ~ y e s,,.,, _u
._,..., *", x ;. s :< q. A. - L 3. vm s.mxa p.,
- p. 43
.n.
-s e
l i
[
ENCLOSURE 6 v
POST-ACCIDENT SAMPLING OF RCS, RB SUMP AND MWST, EMERGENCY COORDINATOR NOTIFICATION
- i i
i List of Personnel Performing Sample Acquisition:
Name Title 1.
2.
3.
4.
5.
Date/ Time of Entry (projection):
/
- Working Copy
- of EM-307 available.
Initials
- To be completed prior to leaving the general assembly area.
For the purpose of sampling the Reactor Coolant System under EM-307.
i EM-307 Rev.' 1 0 Page 47 l y m.,... _ _ _ --
m_O. ag:o.
3Y w ' -
- - - -
- s z c,:
- - n.
= P ".2r-7 ~ " " ~~,-
+
f. "* ;.
L ': < i
y -
1_,
1 u,
....t
.,s
.. -e-s,..
s..
s;,;
r.
\\
.>u..
-u.
ENCLOSURE 7 J
Reen==anded Samole Flush Times em-nle Point
.25 con Flow
.50 com Flow
' Reactor Coolant Letdown 2 hr, 56 min 1 hr, 28 min Reactor Coolant Loop A 8 min 4 min Reactor Coolant Loop B 12 min 6 min Reactor Building Sump 34 min 17 min Decay Heat 6 min 3 min Miscellaneous Waste Storage Tank 4 min 2 min Reactor Coolant Letdown 40 min 35 min PZR Water Space 10 min 5 min PZR STM Space 30 min 15 min
'This sample flush time is based on zero letdown flow.
EM-307 Rev.1 0 page 48
=Mimmn : ' x c
-s
- - a,;, z. - -
- -= m:-
+: - -
__gs < z m.
mm 7.
- 1
..t
)m e
n
- LI 7.8 PRIMING THE ANALYTICAL PUMP OF THE DIONEY 2010 I.C.
7.8.1 STOP the analytical pump.
7.8.2 Insure the correct eluent selector switch has been energized.
7.8.3 To the lef t of the analytical pump is a black block valve with a handle on top and a connector for a 50cc plastic syringe. Connect a 50cc syringe to the block valve and align the valve handle to point down the length of the syringe.
7.8.4 Slowly withdraw the syringe plunger. This should draw eluent from the eluent bottle into the syringe as well as air from the eluent supply line.
7.8.5 Disconnect the syringe from the block valve and expel all air from
'M the syringe. Reconnect the syringe.
7.8.6 Loosen the round black knob that covers the analytical pump outlet two full turns counterclockwise.
This opens the drain line from the pump.
7.8.7 Depress the plunger on the syringe forcing the eluent into the pump.
It should flow thru the pump and to waste carrying the air from the pump with it.
7.8.8 Tighten the covnr knob to close the drain line and return the handle on the block valve to its normal position (perpendicular to the syringe).
Restart the pump.
If pressure will not stabilize repeat 7.8.1 through 7.8.7 until all air is expelled from the f
pump.
1 i
Gkj (LAST PAGE)
EM-307 Rev.10 page 49 l
l
~ '- f.% _. sa Myhi,,,
. ?f?*T. '
lWf&;,
f*"_,
SR
16.
~L.- -
- ~ww.
=%-
_ ~ ~
~
. sun.:,n:
e Rev. 4 12/12/85
/~ s
.'ciiOD t
)
Occurncnt c.
lq
['%. 't.; $b' "
%/
NFORMAme - (> "
c.a.nucgy J
a EMERGENCY PLAN IMPLEMENTING PROCEDURE I.M-305 FLORIDA POWER CORPORATION dRYSTALRIVERUNIT3 POST-ACCIDENT SAMPLING AND ANALYSIS OF EFFLUENT RELEASES FROM THE PLANT 4
USING THE AUTOMATED ISOTOPIC MEASURING SYSTEM (A.I.M.S)
THIS PROCEDURE ADDRESSES NON-SAFETY RELATED COMPONENTS i
l REVIEWED BY:
Plant Review Commi ee k
v Date 12/12/86 Meeting No.
86-49 APPROVED DY:
Dir., Nuclear Plant Operations NYE lt b 9 4 9ys
/
Date
!$L /X
("
i l
INTERPRETATION CONTACT: Nuclear Safety Supervisor f
y, mmy~gav;agyn.;zm:.yge,,. ny,:p -.,..g.
.= _. __
nymy-at."
, :,. M n M,
..~.wss -
; ^
7..._...
- 6.4%i..-
4 TABLE OF CONTENTS (s)
FOR EM-305 s_ '
Page Section 1.0 Purpose 1
Section 2.0 General Guidelines 1
Section 3.0 References 2
Section 4.0 Instructions 2
4.1 Sampling the RB Vent Monitor 2
4.2 Sampling the AB Vent Monitor 3
4.3 Isotopic Analysis 4
4.4 Grab Sampling 8
4.5 Manual Operation of RB LMHvc 12 O)
(,
4.6 Manual Operation of AB LMHVC 14 4.7 System Flush 16 4.8 Filter Replacement in RB Vent Monitor 17 4.9 Filter Replacement in AB Vent Monitor 20 Section 5.0 Calculations 23 Section 6.0 Notifications 32 Section 7.0 Enclosures 33 EM-305 Rev. 04 page i
)
=
4 O,
h4 4
.+.u,'
,f i
s
- * /p
=
m=
- -a..
.a.
. -- -. s - - - - >
e.,.,~-
s, _--e
. ; r_ _.
i
,~_-m.
\\
)
1.0 rumi6H l
)
%J 1.1 The purpose of this procedure is to describe the actions to be taken to sample and analyze effluent releases from the plant under accident conditions within the range of 1.0E-6 to 1.0E5 C1/cc using the RB Vent Manifold, 1.0E-6 to 1.0E3 Ci/cc using the AB Vent Manifold, and the collection of particulate and iodine samples having < 3 Ci with 1000 cc/ min for 30 min 0 100 Ci/cc.
2.0 GENFRAL GUIDET.TMES 2.1 Performance of all or part of this procedure will be done on the instruction and authority of the Emergency Coordinator.
O]
g 2.2 Entries into the AB MUjiI have Health Physics pre-planning, concurrence, and coverage as outlined in EM-208, Duties of the Radiation Emererency Team.
When sampling in the TB, Health Physics coverage should be considered depending on plant status.
2.3 During post-accident
- sampling, extremely high radiation exposure levels could be experienced.
The ability to perform this procedure and stay within exposure limits will require ALARA pre-planning.
2.4 Use Enclosure 1 (Figures 1 thru 3) for designated access route to the RB Vent Monitor, AB Vent Monitor, and Grab Sampler.
EM-305 Rev. 0 4 p g.
- ^^
v h*
- f "=
F.
_.__.:._e w
. -- +;n :. +y.:.
~.,. r31-. _,.... _
w-4~..
.;=a
_wn.
2.5 Return to the Lab if:
,3 2.5.1 The required tools are not in the Post-Accident Sampling Kit per Enclosure 13.
2.5.2 The dose rate at places requiring work is > 15R/HR (the 3 REM limit will be exceeded in 12 minutes at 15R/HR).
3.0 nnvarmtvn 3.1 Radiological Emergency Response Plan 3.2 EM-208, Duties of the Radiation Emergency Team 3.3 NUREG 0737 3.4 Regulatory Guide 1.97 3.5 Drawings FD-302-695, 306-693, 302-694.
Enclosures 10, 11, and 12 are for guideline use only.
OQ 3.6 CH-350, Sampling the condenser off-Gas 3.7 CH-230, Gamma Spectroscopy Utilizing the ND-6685 3.8 AI-1600, ALARA Program Manual 3.9 CH-375, sampling CE-13 and CE-14 4.0 INSTRUC" IONS 4.1 SAMPLING THE RB VENT MONITOR 4.1.1 Ensure the RB LMHVC is in "AUT0" or lined up in manual per N
Section 4.5.
l
(
EM 305 Rev.
Fage 2 lTypM,% vu nnegynowy~~5.w.vey;.wyr.w+. gigs #
'-<:'w*
e;.p w-
\\
.a.
.. w, u-a.
m,. e _ w e
_ % m-ec.
a-.
- m E...=.2... __. 3...: _
m NOTE: The following valves are operated from the Count Room, p
4.1.2 Open RMV-11.
4.1.3 Open WSV-61.
4.1.4 Open WSV-70 (interlocked with WSV-33, WSV-35, WSV-36, and WSV-37).
4.1.5 Start WSP-1*.
$$$$$$ttttttttttttttttttttttttt22999992229899$$t999999999928tt9
' CAUTION: Do not start WSP-1 without a discharge path.
i ttttttttttttttttttttttttttttttttttttttstettttstetteststetttstet 4.1.6 Check flow meter WS-14-FT on the Range Mimic Panel for sample flow.
S]
4.1.7 Go to Section 4.3.
4.2 SAMPLING THE AB VENT MONITOR 4.2.1 Ensure the AB LMHVC is in "AUT0" or lined up in manual per Section 4.6.
NOTE: The following valves are operated from the Count Room.
4.2.2 Open RMV-23.
4.2.3 Open WSV-61.
O a
EM-305 Rev. 0 4 g,y, 3
.$9?DWCE5@ff4= i.9GQ9y#nfe"fri/.'F1 ASS +514%#M!rr#5~455"M'i" -,.~
f-'~
~ :_..
w
..s-
m__m _
-www.; _ -
. < v - e. -r: -
~.a:p......_ _
4.2.4 Open WSV-70 (interlocked with WSV-33, 'WSV-35, WSV-36, and I
h WSV-37).
4.2.5 Start WSP-18 2299tStttttttttttttttttttttttttttttttatstStettettettetttttttste CAUTION: Do not start WSP-1 without a discharge path.
i ttttt2999999999tttttttttttttttttttttttttttttttttttttttttttttt99 4.2.6 Check flow meter WS-14-FT on the Range Mimic Panel for sample flow.
4.2.7 Go to Section 4.3.
4.3 ISOTOPIC w
4.3.1 If an isotopic is required, continue with this section.
If an isotopic is not required, go to Section 4.7.
NOTE: Prior to continuing with this section insure the following concerns are met:
1.
Detector should have an adequate supply of LN -
2 2.
HV should be correctly applied to the RANGE Detector and not disabled via the LN2 monitor.
N EM-305 Rev. 0 4 p,q.
4 V'.T<Q' sw;7ki,@bMgJiQu'tM.Qs%MLgd 'w~^ry?;66 s *WGg%v M7
'"M &a
"' - n- - - --
2 2. s.w s x
=
-n:.
a
.t.
2-~-
=
-+
w w===e w-n m n +me-v w_
. M-<.mL.3 : _,;_,-
sessenensesessenessmennesses.... ensessenessessenessensensente
/%
/
i V
CAUTION: ]EEER resest the HV using the LN2 monitor ' RESET' switches.
ALWAYS lower the HV bias voltage to 0 volts before resetting the LN2 monitor.
3.
' PASS
- printer has an adequate supply of paper and the printer ' READY" light is illuminated.
4.
The disc drive ' READY" light is illuminated.
5.
A daily detector calibration using the jobstream AUTO. CAL 2 should have been performed.
6.
Due to jobstream flow and function, do not
- attempt to simultaneously perform both liquid and gas sample analysis.
R$$221stttt 2992223229tittttttt22222292229999999922999999922222 n) 4.3.2 Sign on the ND-6685 computer by entering:
(V s
HEL 2
<CR)
USER 2 (CR)
NOTE:
(CR) is the symbol for carriage return and must follow each input.
1 i
4.3.3 Start the jobstream as follows:
JOB AUTO. RANGE l
1 1
1 l
l l
Rev. 0 4 EM-305 Page 5 T*c *..m~*A.cw i "2 i..a > 'i:'. r. 'ii. ": < &..
'"r.-**"'.~=L
" ' " " ' * " * ' * ~*** '#
~ ; *' "
- ~ ".,, ' " _ ~~~ ^ ' ' ' ~
-~
'h
_,i
_ n,_
m.-- w =- w -..--.
4.3.4 The computer will prompt:
fs WHAT DO YOU WISH TO SAMPLE?
(1) REACTOR BUILDING ATMOSPHERE (2) REACTOR BLDG VENT / AUX BLDG VENT (3) NONE (END THE JOBSTREAM)
Enter
'2".
4.3.5 The computer will display the parameters from the last isotopic analysis performed and prompt:
DO YOU WANT TO UPDATE PARS (U) OR EXIT (E)?
Enter 'U" to update parameters.
NOTE: Correct volume will be calculated by ND6600.
Enter return when asked for volume.
O r
4.3.6 The computer will reprompt:
\\
00 YOU WANT TO UPDATE PARS (U) OR EXIT (E)?
Enter "U" to correct any errors.
Enter "E" to Exit.
4.3.7 The computer will automatically perform the analysis and print out a header and peak search on the line printer.
AU EM-305 Rev.0 4 pay, e
&- [jffa % lM5 S. i?%9.hii $ iki $c @CG.Q & sNE.; w b[' $Jsl % % % ' W * % Ysk N 6 'N.+ - s-a:
s--
x
. a y. 4 f
"?.
.e s-
~
w -
c.
,=.-.
,m m.
- - m,,_ -,.c.,,g,,.
- .,
- - -- -Qzy --
4.3.8 The computer will prompt:
)
SELECT THE DESIRED REPORT TYPE (1) FLOWING SAMPLE
SUMMARY
REPORT (CMSUMR)
(Normally required)
(2) FLOWING SAMPLE MDA REPORT (CMMDA)
(3)
FLOWING SAMPLE EBAR REPORT (CMEBAR)
(4) FLOWING SAMPLE IODINE REPORT (CMIEQ)
(5) STANDARD GSP SHORT REPORT (GSSRPT)
(6) STANDARD GSP LONG REPORT (GSLRPT)
(7) STANDARD GSP MDA REPORT (GSLLD)
Enter the number corresponding to the desired r'eport type.
NOTE:
If in doubt as to which report to select, contact Chemistry Supervision.
,m
'I I
\\_/
4.3.9 The computer will print out the requested report and then prompt:
DO YOU WANT ANY ADDITIONAL REPORTS?
1.
YES 2.
NO Enter "1" for YES, or *2' for NO.
Answering
'1' (YES) will restart the jobstream at Step 4.3.8.
Answering "2" (NO) will cause the computer prompt:
[
)
C/
EM-305 Rev 0 4 Page 7 f
fg 8,,. vean.;;g_. uWG.;,,ggc2 ;sowYgne%w..w als < a.
4
_1
~
2._.
t.;.._.. ;..... :.. ' -
p_g:
wmm&r-m< ~.w
/+m r --
4.3.10 DO YOU WANT TO PERFORM ANY ADDITIONAL ANALYSES?
-s 1.
YES 2.
NO ANSWERING *1" (YES) will restart th*. jobstream at Step 4.3.4.
ANSWERING
'2" (NO) will cause the computer to prompt:
ALIGN VALVES TO BEGIN INSTR. AIR PURGE Go to Section 4.7.
4.4 GRAB SAMPLING NOTE: Entries into the AB JEiI have Health Physics pre-planning, concurrence, and coverage as outlined in EM-208, Duties of the Radiation Eneroency Team.
Return to the Lab if:
The dose rate at places requiring work is ) 15R/HR.
(The 3 REM limit will be exceeded in 12 minutes at 15R/HR.)
Use Enclosure 1 for access route.
4.4.1 In order to perform grab sampling, the correct valve alignment m'ast ba established before proceeding to sample area.
4.4.2 Open RMV-11 for RB vent grab sample or RMV-23 for AB vent grab sample.
NOTE: These valves are operated from the Ranga Mimic Panel located in the counting room.
O EM-305 Rev.0 4 3
page a
.;f,,,;;fghuwsgngw?s4;-g?;;;45fW+Egqg.r-we pt s >.r-uvMw -s-t;, f.
~ w2
.q,.
. ~ _.
a s u
.?_
.u,.
w rer; w,r:=r x w
=w 3.x _... ;.
L.
\\
1 i
4.4.3 Open WSV-59 and WSV-60.
This aligns the flow path through the
/
T V
grab sampler.
4.4.4 Open WSV-70 (interlocked with WSV-33, WSV-35, WSV-36, and WSV-37).
ttttt9ttttttttttttttttttttttttttttttttttttttttttttttttttttttttt CAUTION: Do not start WSP-1 without a discharge path.
htttttttttttttttttttttttttttttttt999999999999999999999999999999 4.4.5 Start WSP _1.
4.4.6 Check flow meter WS-14-FT on the Range Mimic panel for sample flow indication.
4.4.7 Allow 5 minutes for sample co purge through the grab sampler.
4.4.8 Proceed to grab sampler location.
t 4.4.9 Ensure that the exhaust fan directly above the sampler is L
turned on.
The switch is located adjacent to grab sampler.
4.4.10 Using the T-handle, turn the grab sampler 3-way valves fully clockwise to isolate the sample in the samp,le bomb and direct all the sample flow through the internal bypass line.
4.4.11 Return to the counting room and initiate a system flush.
4.4.12 Open WSV-63.
4.4.13 Close RMV-11 or RMV-23 whichever is applicable.
4.4.14 Optr WSV-61.
4.4.15 Close WSV-59 and WSV-50.
4.4.16 Flush for at least 2 minutes.
4.4.17 Turn off WSP-1.
O
\\j EM-305 Rev. 0 4.
p,y, 9
-} T ' A;_ +:n;[A% '::a.+f5 Q' gggy:Qn,&h?.WMO:
- sn: e.~.'a.
cu- +."4.--
- 3t,
na r _s c +
h Mny,.g... ;a. x:-~;.m.m.wc%u. m-:m.q. _..,.. ..m,. 3v e 4.4.18 Close WSV-63, WSV-61 and WSV-70. f3 V 4.4.19 Return to the 143' elevation of the Auxiliary Building and obtain an adjustable wrench and one transit cover from the Post-Accident Sampling Kit. 4.4.20 Proceed to grab sampler area. Remove the ramp with the adjust-able wrench. 4.4.21 To remove the grab sampler, install the ramp in front of sample station. 4.4.22 Disconnect Grab Sampler from the sample station by squeezing the disengagement lever and by pushing the engagement handle to its rearmost position. 4.4.27 Pull up on the handle of the cart locking mechanism to release the cart. 4.4.24 Remove the Grab Sampler and cart to a low radiation area and ) install the transit cover over the quick-connects. uJ 4.4.25 If it is necessary to install a new sampler, proceed to Steps 4.4.26 thru 4.4.36. If it is not necessary to install a new sampler, proceed to Step 4.4.37. 4.4.26 To install a new Grab Sampler, mount the Grab Sampler onto the cart and remove the transit cover. 4.4.27 Using the T-handle, position the Grab Sampler 3-way valves to the fully counter-clockwise position for sampling. 1 I tO) %/ l EM-305 Rev.0 4 page 10 cww. w am;w.,...w.= xn w-Tpa- . :nw. .: w. _._, _, w., ~ t =W~ . w :. ._a ~,
M-3: s-a . g __--- - ---- ..ep* m~,r,., j_, 4.4.28 With one person guiding the sampler assembly, another person O) / should push it up the ramp and onto the platform, halting several inches from the connection points. tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttts CAUTION: When ~ connecting the sampler, force should NEVER be used. Damage to the quick-connects will result from forcing the connection. $99999129999999922t$$$$$$$199999999999991222$$222222999999t$292 4.4.29 Very carefully, slowly push the sampler into the sample station. If positioned correctly, the front of the sampler will make metal-to-metal contact with the curved face of the sample station. r% (J 4.4.30 Additionally, proper alignment is indicated by being able to i engage the cart-to-station locking mechanism. 4.4.31 If the sampler does not position correctly, pull the cart back i a short distance and realign it. 4.4.32 Repeat Step 4.4.29 to position sampler. Repeated Ettempts may be necessary for proper alignment. Lock the cart to the station by pushing the handle of the locking mechanism completely down, driving the lock-bolt through the hole in the cart. rm i \\ \\_) EM-305 Rev. 0 4 eage 11 ]Q.. a... - f! ch'sshWe+3pwiW. 2A'-$pgja97 e : -W.mty -*- Q-ipz. en a:n.- u. _a. a , ~ _ ~
'mM^W yvr.xu+a-g %; _.'.r-:l eWNn%;.;. -.+ :T.: w Q Q..,.__. ; ' ; l 4.4.33 Gently pull the engagement lever forward until a distinct ,7U ' click *is heard (the lever must HQI be forced). This signifies that the quick-connects have engaged. NOTE: Due to environmental conditions, the click may not be heard. 4.4.34 To insure engagement, unlock the cart from the station and move the engagement lever back and forth. If properly engaged, the cart will also move back and forth. 4.4.35 Re-lock the cart to the station. 4.4.36 The Grab Sampler is now ready for use. 4.4.37 Transport the grab sample just obtained and its cart to the appropriate area. The grab sampler can be removed from its ID (j' cart and transported off site. 4.5 MANUAL OPERATION OF RB LMHVC 4.5.1 At the LMHVC in the Main Control Room, position toggle switches so that the valve controller lights match the ' AUTO' positions. 4.5.2 Position the auto-manual switch to " MANUAL". rh (,.J) EM-305 Rev. Page 12 f.:5;r:?,m.wn ens,aywmy m=~na.aw-+ - ~=u.v: -,,-:-- m - - - a s. % ~ ?'"W;D
- c. -
t a
- - -..,. m,,;... _ - _w g,,_ NOTE:
- 0g= indicates 'OPEN", "0FF" indicates ' CLOSED *.
/% i \\ 'O 4.5.3 For low range (normal operation-manual): Turn '0FF" valves RMV-003, RMV-004, RMV-005, RMV-008, RMV-009, and RMV-006. Turn 'ON" valve RMV-025 (Automatic when RMV-008 is turned "0FF'.) Observe flow on RM-Al-FT at RANGE Mimic panel, should be approaching zero. 4.5.4 If the low range radioactivity level exceeds one half the range of the low range indicating instrumentation (10-2 uCi/cm3), adjust valves as follows to direct flow to the mid-range detector: Turn *0N' valves RMV-004, RMV-008, and RMV-009. %Y Turn '0FF" valve RMV-025 (Automatic when RMV-008 is turned 'ON') 4.5.5 After a minimum of thirty-five (35) minutes turn "0FF" valve RMV-009 and check that the radioactive sample has been flushed from the low range detector.' (Low reading on Victoreen meter). 4.5.6 If the mid-range radioactivity exceeds three-fourths range of 3 the mid-range indicating instrumentation (.01 to 10 mR/hr) and 7 the high range monitor (.1 - 10 mR/hr) is on scale, adjust valves as follows to direct flow to the high range detectcr: Turn "0N" valves RMV-005, RMV-006, and RMV-003. Turn '0FF" valve RMV-004 O EM-305 Rev.0 4 page 13
- .;Qiy6%iu%f?Wt3M%
- Q
- s-?:4GR %%d:~ W m!Ny&fW~M M%RM6ty";^f~.
C;G " '~ " t _,, m,.- -=.
- 1 - cm
.a-e:.--
xx.. : :..% w ,:.,,.. s a n... ,w ~ g, az.g. : a. m;w.:w%. ; ,c Is ( 4.5.7 Af ter thirty-five (35) minutes, turn '0FF" valve RMV-003 and check that the radioactive sample has been flushed from the mid-range detector. (Low reading on Victoreen meter). 4.5.8 If radioactivity levels reduce to low or mid-ranges, return valves to the position corresponding to that level. See Enclosure No. 4. NOTE: In " Auto" mode the mid-range detector must be manually purged on decreasing radiation levels by turning "0FF" valves RMV-3 and RMV-6 for 35 minutes. 4.6 MANUAL OPERATION OF AB LMBVC 4.6.1 At the LMHVC in the Main Control Room, position toggle switches (S (,) so that the valve controller lights match the ' AUTO' positions. 4.6.2 Position the auto-manual switch to " MANUAL". NOTE: 'ON' indicates 'OPEN', '0FF" indicates ' CLOSED *. 4.6.3 For low range (normal operation-manual) Turn "0FF" valves RMV-015, RMV-016, RMV-017, RMV-020, RMV-021, and RMV-018. Turn 'ON" valve RMV-26 (automatic when RMV-20 is turned '0FF'). Observe flow on RM-A2-FT at RANGE Mimic Panel, should be approaching zero. rN (v) EM-305 Rev. Page 14 n;:gw?wqsigw,,-n. veqyp.~.m:.:-cm > +:a.-o c: s w.w -m-w:r ww sque.XT' 1
MOSL.- _..,L. :rlO C.%..-:.. G_ T :J.. 3 W _ j_^ ^,'~ L, -; T Q.., _. f f;-3.;.g. r. ~ 1 - a 4.6.4 If the low range radioactivity level exceeds one half the range I \\ 'd of the low range indicating instrumentation (10-2 uCi/cm ), 3 adjust valves as follows to direct flow to the mid-range detector: Turn 'ON" valves RMV-016, RMV-020, RMV-021. Turn *0FF" valve RMV-026 (automatic when RMV-020 is turned "0N"). 4.6.5 Af ter a minimum of thirty-five (35) minutes, turn *0FF" valve RMV-025 and check that the radioactive sample has been flushed from the low range detector. (Low reading on Victoreen meter). 4.6.6 If the mid-range radioactivity exceeds three ~ourths range of 3 the mid-range indicating instrumentation (.01 to 10 mR/hr) and 7 the high range monitor (.1 10 mR/hr) is on scale, adjust valves as follows to direct flow to the high range detector: p Turn 'ON" valves RMV-017, RMV-018, and RMV-015. Turn '0FF" valve RMV-16, 4.6.7 Af ter thirty-five (35) ainutes, turn '0FF" valve RMV-015 and ~ check that the radioactive sample has been flushed from the mid-range detector. (Low reading on Victoreen meter). 4.6.8 If radioactivity levels reduce to low or mid-ranges, return valves to the position corresponding to that level. See Enclosure No. 5. NOTE: In Auto mode the mid-range detector must be manually purged on decreasing radiation levels by turning "0N" RMV-15 and RMV-18 for 35 minutes. Ob 4 EM-305 Rev. Page 15 4feSN' "AMy.+A. yggsWea.W7?+3n$Ee E9i?W@p%_ ii 'e 'iW+%Wes t-o * ,z 2;&n;n Y_" --/ V- -. _ - w.. w --
~ - ,,a.... ... = <-,y,. . ;. y3_;. ?--- ,. = - , g;n,. ~,,,_ g_.w.,...a,..,... _. '-'s 4.7 SYSTEN FLUSH ) 'v 4.7.1 Open WSV-63. 4.7.2 Close RMV-11 if sampling RB Vent Monitor. Close RMV-23 if sampling AB Vent Monitor. 4.7.3 Allow inst. air to flush for 5 minutes. 4.7.4 Acquire a manual spectrum. If a high countrate is indicated, continue flushing. If a low stable countrate is indicated, answer the computer prompt: ARE YOU FINISHED FLUSHING? With
- 1' (YES).
4.7.5 Sign off the ND-6685 by entering: ' BYE 1' k_- 4.7.6 Turn off WSP-1. 4.7.7 Close WSV-63. 4.7.8 Close WSV-61. 4.7.9 Close WSV-70. (O ,_ / EM-305 Rev.0 4 .] Page-16 mghmE%ng. n:g 7.w. ?nwcmcasma.-;*; sm.ss+wu.ws.e.u. n .w-c . i. ~ a_
g. n,.;
- n.,
my, &n= - ._ ~ _ - a:n w ~; sm:.,,~, e.--4,. ~ w.. g g: ,,_,z;; _.3 4.8 FILTER 95'DLACBEENT IN RB VENT MONITOR (RM-A1) / t u,' NOTE: Entries into the AB lEL1I have Health Physics pre-planning, concurrence, and coverage as outlined in DE-208, mities of the Radiation Enercency Team. Return to the Lab if: The required tools are not in the Post-Accident Sampling Kit per Enclosure 13. The dose rate at places requiring work is > 15 R/HR (the 3 REM limit will be exceeded in 12 minutes at 15 R/HR). Use Enclosure I for access route. 4.8.1 Chemistry Supervision shall determine sample flush times based on current plant conditions. i% [ \\ (,/ 4.8.2 Note flow on RMA-1-F1 at RANGE Mimic Panel. 4.8.3 Proceed to Post-Accident Sampling Kit located on 143' elevation of Auxiliary Building. 1 4.8.4 Obtain the following equipment from the kit:
- 1) Sample cartridge lever, 2) tong extractors, 3) new filter & cartridge (2), 4) Plastic bags, 5) Shielded carrying container.
4.8.5 Proceed to RMA-1. 4.8.6 While monitoring local radiation levels, remove old filter cartridge from PGS-2 (off service filters) and replace with a new filter cartridge. Depending upon the activity levels, it may be necessary to use the sample cartridge lever and the tong extractor for the above evolution. See Steps 4.8.16 thru 4.8.18. O V EM-305 Rev. 0 4 Page 17 i&cgger++ sergnW+w VMMATEG5MR/+v+a#EWF >%i%We ~E G
- n.- 7,...:g :-.:, n enp ;p. evt.7., v, - r M:9 8., .. L.. b- & c .~ - ~ - z..- x .w:w % ~ sedk~ - - m mD= --- ~ M *RS ~ = w ._M2 L = = a = ('N 4.8.7 Discard old filters into proper receptacle. / U 4.8.8 Reverse the positions of the 3-way manual valves RMV-001 and RMV-002. This is the sample start time. NOTE: When the valve handles on RMV-001 and RMV-002 are in the vertical position, flow is going to PGS-1. When the valve handles for RMV-001 and Rh7-002 are in the hori-zontal position, flow is going to PGS-2. 4.8.9 Reduce radiation exposure as much as possible by leaving the immediate area during waiting periods (i.e. flush) and also use portable shielding if possible. 4.8.10 Again on instructions from the Emergency Coordinator and under the direction of the Radiation Emergency Team, return to RM-A1. V 4.8.11 Upon arriving at RM-A1, reposition valves RMV-001 and RMV-002 to place other PGS in service. This is the sample end time. 4.8.12 Open valve RMV-27 for PGS-2 or RMV-119 for PGS-1 to purge sampler with instrument air for five (5) minutes. 4.8.13 Reduce radiation exposure as much as possible by leaving the insediate area during waiting periods. 4.8.14 After 5 minutes close RMV-27 or RMV-119 depending on which filter is being replaced / purged. 4.8.15 While monitoring local radioactivity, lift latch and open shield door with care. Reclose door immediately if radioactiv-ity is higher than planned. Retreat and replan. [\\ EM-305 Rev.0 4 Page 18 I Q:IdN 8i%25 % f % @ t%* Y W 7 E"OAA N Y h d 4-+ '.-U1 h I
s-m,, s.
- f. : f. 7
- ~~.,.,<
.m-., . -...,.rs.. _ ~ - m, ,. e. ; _._.... t n. u ,..m._. m.. a, , -h 4.8.16 With door open, release the spring held filter cartridge by use '~' of the sample cartridge lever and its extension rod applied to ) hole just below the filter (counter-clockwise motion). i 4.8.17 Insert tong extractors and grasp the cartridge firmly and place cartridge in a plastic bag and shielded container. 4.8.18 Replace old filter with new filter and close door. CAUTION: When tightening with cartridge lever, do not use excessive force as damage may occur to lever tip or handle. 4.8.19 Move old filtc4 to storage location or to place of analysis as (_.) directed. 4.8.20 Corrected volume is cc = total time x cfm x 2.832E4 x.95. n ( ) s_/ EM-305 Rev. Page 19 ~7l53-Wwr.--me.85.g'?ve.+,wusgq+s,:;c,.8:n.inys77WM.'*BER*T;' = m. .. _ ~ ~ ~ ~ ~ ~
- y. y y.
c T*w~.u~.. 33~.- - _. y ,wn, _,. 1 <_. -,. s. g.;.g y.. y.f, ....rg., ,,,;,,j,._,,_ _.u_ .f e.m c.t_-- e 13 4.9 FILTER nrDLACDENT IN AP VENT MONITOR (RM-A21 I.v] NOTE: Entries into the AB MUST have Health Physics pre-planning, concurrence, and coverage as outlined in EM-208, Duties of the Radiation Enercency Team. Return to the Lab if: The required tools are not in the Post-Accident Sampling Kit per Enclosure 13. The dose rate at places requiring work is > 15 R/HR (the 3 REN limit will be exceeded in 12 minutes at 15.R/HR). Use Enclosure 1 for access route. 4.9.1 Chemistry Supervision shall determine sample flush times based on current plant conditions. in. C), 4.9.2 Note flow on RMA-2-FI at RANGE Mimic Panel. 4.9.3 Proceed to Post Accident Sampling Kit located on 143' elevation of the Auxiliary Building. 4.9.4 Obtain the following equipment from the kit:
- 1) sample cartridge lever, 2) tong extractors, 3) new filters cartridge (2), 4) plastic bags, and 5) shielded carrying container.
4.9.5 Proceed to RMT-2. 4.9.6 While monitoring local radiation levels, remove old filter cartridge from PGS-4 (off service filters) and replace with a new filter cartridge. Depending upon radioactivity levels, it may be necessary to use the cartridge lever and the tong extractors for the above evolution. See Steps 4.9.16 thru 4.9.18. 'w/ EM-305 Rev. Page 20 3 5.5csu w G @Ae, m A can.g.wmw.-w.s.4wAM'U73Wmh. ^ -'^ : ' - ~ ~ 3
ny g. 7,. ..c.,,.n,..,.,.. m. ..v-m.e a., a .j.3 : ao.s. /. m.,,p.
- WM 7.s s.._:,, r-
_ D Y _w-ca t?.,f 5. g..,3...f,,,,, Q71& _ _,. y;pg? y l, ;- 4 (h 4.9.7 Discard the old filters into proper waste receptacle. 1 4.9.8 Reverse the positions of the 3-way manual valves RMV-013 and RMV-014. This is the sample start time. NOTE: When the valve handles on RMV-013 and RMV-014 are in the vertical position, flow is going to PGS-3. When the valve handles on RMV-013 and RMV-014 are in the hori-zontal position, flow is going to PGS-4. 4.9.9 Reduce radiation exposure as much as possible by leaving the immediate area during waiting periods, (i.e. flush) and also use portable shielding if possible. 4.9.10 Again on instructions from the Emergency Coordinator anc under the direction of the Radiation Emergency Team, return to RM-A2. d 4.9.11 Upon arriving at RM-A2, reposition valves RMV-013 and RMV-014 to place other PGS in service. This is the sample end time. 4.9.12 Open valve RMV-33 for PGS-3 or RMV-34 for PGS-4 to purge sampler with instrument air for five (5) minutes. 4.9.13 Reduce radiation exposure as much as possible by leaving the immediate area during waiting periods. 4.9.14 After 5 minutes, close RMV-33 or RMV-34 depending on which filter is being replaced / purged. 4.9.15 While monitoring local radioactivity, lift latch and open shield door with care. Reclose door immediately if radioactiv-ity is higher than planned. Retreat and replan, i I ( i EM-305 Rev. 0 4 eage 21 - x -x 5,4phv.,. _ _,:=~~":' '~L*m"K@yEnsw;s.may._- __,p.y=niaysy.qq~7~Wyggtw,GMOTs?:W '~ - - w m.- -=..
- L_.y ~.
..1.sE:2A:3.r _,,ee..;.._,; _q%; y a._ y,., p r'.';k... _.. g]).; ..y u.g - 4,:. ,,.., <. a., .v. ..... ~ ..,v..,. ,,...g... _}^- 4.9.16 With door open, release the spring held filter cartridge by use of the sample cartridge lever and its extension rod applied to the hole just below the filter (counterclockwise motion). 4.9.17 Insert tong extractors and grasp the cartridge firmly and place cartridge in a plastic bag and shielded container. 4.9.18 Replace old filter with new filter and close door. CAUTION: When tightening with cartridge lever, do not use excessive force as damage may occur to lever tip or handle. g Move old filter to storage location or to place of analysis as 4.9.19 i I '/ directed. 4.9.20 Corrected volume is cc = total time x cfm x 2.832E4 x 0.95. /~'s \\n.-) EM-305 Rev. 0 4 j page 22 WHE:'*ypnzhv2;.a m..,>.imppswr+:: -i::a:.w.w,-;. -=T W
,..s.-. my ..;..~,. . ;.,. _ c.n,g.y.. 7,- ; _,t,, ~a v:_ c mv-e,a.;yyy.g ~s a.t., .,,.2.._ .,; y,.we,.,. t m _.,._ - _. m 5.0 (*1LCULATIONS ) v 5.1 NOBLE CAR RMJME EVALUATION FROM STEAM RUSAME NOTE: If plant conditions permit, utilize CH-269, Sections 9.5 and 9.6 in place of this Section 5.0. Spectrum acquisi-tion of RM-A1 and RM-A2 will be by the AIMS with Chemistry Supervision transferring the data from the PASS to the ALARA computer. 5.1.1 If the following parameters are met, then the calculation of gaseous releases can proceed as described in Step 5.1.1.1. If any of these parameters are not met, proceed with Section 5.1.2. tV ': a. Unit did not experience loss of off-site power, or loss of condenser vacuum, or loss of bypass steam. (MQ) b. RM-A12 did not indicate a significant and sustained count rate increase (factor of 10 or better), or failure, or spurious high alarms. 5.1.1.1 Obtain the data from the last RM-A12 noble gas sample and record the results on Enclosure 2. 5.1.1.2 Record percent full power at time of trip and percent full power at the time of the last RM-A12 sample. (If not known, input 100\\). Record on Enclosure 2. 5.1.1.3 Determine the duration in seconds that the steam was being released to the atmosphere and record on Enclosure 2. i 1 'O EM-305 Rev. 0 4 ] page 23 ???? 5$$??i$5S???$5???NON'S' '#' ' ? " ' =-
.yn. -c
- ,...c.
...y m-x....w. . e...ema.,., ~.m.,v a ne x _., _..: n.-, c.. c-
- n,,.
.g, ,3 ~ 5.1.1.4 Using the following formula, determine the total curies ' ~' released: A = (C) (600 cfm) (28,317 cc/cu.ft.) (1 min.) (T) (IE ) T 60 sec. fps WHERE: A = Total uCi released C = Concentration of noble gas at RM-A12 in uCi/cc. 600 = Flow rate past RM-A12 in cfm. 28,317 = Conversion from cubic feet to 'ce" 1 = Conversion from minutes to seconds 60 T = Duration of release in seconds FPT= Percent full power at time of trip in decimal form FPS = percent full power at time of sample in decimal r x, form ( ) To convert uCi to C1, multiply by 1 x 10-6, 5.1.1.5 proceed to Section 5.2. 5.1.2 If the following parameters are met, then the calculation of gaseous releases can proceed as described in Step 5.1.2.1. If any parameters are not met, proceed with Section 5.1.3. a. Unit did not experience a loss of off-site power, or loss of condenser "acuum, or loss of bypass steam. (AU.2) b. RM-A12 count rate showed a substantial increase at the time of the trip (2 10 times increase), or failure, or spurious high alarms. 77 ( ) x -- - EM-305 Rev.0 4 page 24 T T.R & W U w d pfl E N E. W I'F E W E w N @ y e-W 3 - '-N 22e-6~ ~ ~ ~ EETZ"' 3.s
- ,...n.'_<,
- ..,. 4v, +.e
- =u t..,., g. 9; ~ ~. p in u,..
- .,=.
&%9n3..' c wa;M??Y.k:at. +mi , w:;.i.yyuu. > elOWTw:a . v?*h Jl. * ~ ..'.r.:..* [m, 5.1.2.1 Record the percent full power at the time of the trip on 5 / '~'. 5.1.2.2 Determine the duration in seconds that the steam was being released to the atmosphere and record on Enclosure 2. 5.1.2.3 Obtain a sample from RM-A12 per CH-350, Samoline the condenser off-Gas. Analyze the sample in accordance with CH-230, Camma Soectroscooy Utilizine the ND-6685. 5.1.2.4 Record the results on Enclosure 2. 5.1.2.5 Using the following formula, determine the total curies released: A = (C) (600 cfm) (28,317 cc/cu.ft.) (1 min.) (1 - 2 ) (T) 60 sec. FPT WHERE: A = Total uCi released C = Concentration of noble gas at RM-A12 in uCi/cc. 600 = Flow rate past RM-A12 in cfm. 28,317 = Conversion from cubic feet to 'ce" _.1 = Conversion from minutes to seconds 60 FPT = Percent full power at time of trip in decimal form T = Duration of release in seconds 1 .J.1 a Allows for 15% bypass flow to the condenser. FPT To convert uCi to C1, multiply by 1 x 10-6, 5.1.2.6 Proceed to Section 5.2. \\ EM-305 Rev. 0 4 page 25 I
.n.~r, _.[g-- -3 3 - =-- -- -
:.n;,2 n:.. n. m.w: -..m._, +> :-a,,
. m... n x_ n _,,, .y 5.1.3 If the following parameters are met, then the calculations of gaseous releases can proceed as described in Step 5.1.3.1. If a parameter is not met, re-evaluate unit conditions for appro-priate method of calculating noble gas releases, then proceed to Section 5.2. a. Unit experienced loss of off-site power, or loss of conden-ser vacuum, or loss of bypass steam. 5.1.3.1 Obtain a sample from each OTSG shell side per CH-342 (343), Samolina Steam Generator 3A (3B) Shell Side, and analyze for dissolved noble gases per CH-230, Gamma Spectroscopy Utilizine the ND-6685. Record the highest activity of the two samples on in uCi/cc. 5.1.3.2 Determine the main steam temperature and pressure at the time of the release. Use these to determine the specific volume of i I the steam using the program SpVOL under misc. programs from the AUTO RUN JOBSTREAM, or Steam Tables and record or. Enclosure 2. 5.1.3.3 Determine the percent full power of the unit just prior to the trip and the duration in seconds that steam was being released to the atmosphere. Record on Enclosure 2. 5.1.3.4 Using the following formula, determine the total curies released: A = (C)(11.2 x 106 lbs/hr.)(V cu.ft./lb.)(28,317)( 1 hr )(T)(FpT) 3 3600 sec. WHERE: A = Total uCi released C = Concentration (uci/cc) of noble gas in the highest activity OTSG shell side sample /m I ) L) EM-305 Rev. 0 4 ] page 2s Tr]?SC'QhTL:Ci~R&:5@4 Q &iRFEM W Q Q 'WVfkW ' 5 V'C ' u' ~ ~
- $ hn'?"Il'.-bul.O SqT Q L'.:n-+ w.l .&s . _. _.. :y, 3 - -'-- NOTE: One OTSG can be used to cool RCS. This must , -_ s / h 5 j \\/ be determined and only the sample from the active OTSG utilized. 11.2 x 106 = Steam flow from both OTSG's at 100$. full power. If only one OTSG is being used to cool RCS, this value becomes 5.6 x 106 lbs./hr. V = Specific volume of steam 3 28,317 = Conversion of cubic feet to *ce" 1 = Conversion of hours to seconds 3600 T = Duration of release in seconds FrT = percent full power at time of trip in decimal form ,O To convert uCi to Ci, multiply by 1 x 10-6, i i / 5.2 RADIOIODINE R5'T.FASE EVALUATION FROM STEAM RELEASE 5.2.1.1 If the following conditions are met, then the calculation of radiciodines released can be calculated as described in Step 5.2.1.1. If any of the parameters are not met, proceed with Section 5.2.2. a. Unit did not experience loss of off site power, or loss of condenser vacuum, or loss of bypass steam. (AE) b. RM-A12 did not indicate a significant and sustained count rate increase (factor of 10 or more), or failure, or spurious high alarms. / h. t i \\. j' EM-305 Rev.0 4 Page 27 [ 7 G M *Q 2 1.ayn pp.%:WP.;'?2E.id:f 'i' ' ' a.:,W: - ST3 ' ~~~ ~~.- C '~
2 %W ..u.. soc "2 ,%.'w. .x.,.g.,...:?' ga _ _. _ _,. ..= _ _, _ ~ 5.2.1.1 Obtain the data from the last main steam resin samples (CE-13 i and/or CE-14) or remove the columns now on-line if its been on-line at least 4 hrs. per CH-375, Samplina the Main Steam Header for Fission and Corrosion Product Activity and analyze for radiciodines per C3-230, Gamma Soectroscopy Utilizina the ND-6685. Record the highest activity of the two samples on. 5.2.1.2 Determine the duration in seconds that the steam was being released to the atmosphere and record on Enclosure 2. 5.2.1.3 Record percent full power at the time of trip and percent full power at the time of the last CE-13/14 sample. (If not known for last CE-13/14 sample input 15 *.. ) Record on Enclosure 2. 5.2.1.4 Determine the main steam temperature and pressure at the time of the release. Use these to determine the specific volume of (_.,) the steam using the program SPVOL under misc. programs from the AUTO RUN JOBSTREAM, or Steam Tables and record on Enclosure 2. 5.2.1.5 Using the following formula, determine the total curies released: A = (C)(11.2 x 106 lbs/hr.)(V cu.ft./lb.)(28,317)( 1 hr. )(T)(IET) 3 3600 sec. Fps WHERE: A = Total uCi released C = Concentration of radioiodines in the highest activity main steam resin sample. The analysis of these samples allows for the input of the sample volume. The volume used shall be the total amount of sample passed through the column in 'cc' / ( / R] EM-305 Rev. Page 28 ~~}~; 1,__ gr 39 %.pn&& mcm.y, .w - .zgTW . ;u ...a c._ Z e.
Ql% F.. 2.sk;.. a x :.: i,L a _ h: &. w.EL. A '.2. x. %.a.:.._;... ;. _. 2---~ ~ ~ - Vs
- Specific volume of main steam in cu. ft./lb.
V) ( 11.2 x 106 = Steam flow at 100*. full power from both OTSG's. 28,317 = Conversion of cubic feet to *cc". 1 = Conversion of hours to seconds 3600 T = Duration of release in seconds FPT = Percent full power at time of trip in decimal form FPS = Percent full power at time of sample in decimal form. To convert uti to Ci, multiply by 1 x 10-6 5.2.1.6 proceed to Section 5.3. 5.2.2 If the following conditions are met, then the calculation of radioiodines released can be calculated as described in Step fG 5.2.2.1. If any of the parameters are not met, re-evaluate V unit conditions for appropriate method of calculating the required data, then proceed to Section 5.3. a. Unit experienced loss of off site power, or loss of conden-ser vacuum, or loss of bypass steam. (OR) b. RM-A12 indicated a substantial increase in count rate () 10 times normal) or failure of monitor or spurious high alarms. 5.2.2.1 Obtain OTSG shell side samples per CH-342 (343), samoline steam Generator 3A f3B) shell side and analyze for radiciodines per CH-230, Ga=== spectroscocy Utilizine the ND-6685. Record the highest activity of the 2 samples on Enclosure 2 in uC1/cc. N' _) EM-305 Rev. 0 4 page 29 .....I [ l j -.9 -> ry?..as. w p a + v~.m. n:g.[ C*k W } }.~ T~~.="O gl.D '
l't:.fi. wziv.'_.~,. . Wg.,:. ;,, _,..s.5,.,c ... s._.::.g n46.' c c..,..; ,d'_ 5.2.2.2 Determine the main steam temperature and pressure at the time of the release. Use these to da.termine the specific volume of the steam using the program SPVOL under " Misc programs' from the AUTO RUN JOBSTREAM, or Steam Tables and record on Enclosure 2. 5.2.2.3 Determine the percent full power of the unit prior to the trip and the number of seconds steam was released to the atmos-phere. Record on Enclosure 2. 5.2.2.4 Using the following formula, determine the total curies released: A = (C)(11.2 x 106 lbs/hr.)(v cu.ft./lb.)(28,317)( 1 hr. )(T)(FpT) s 3600 sec. WHERE: A = Total uCi released C = Concentration (uci/cc) of radiciodines in both p/ OTSG shell side samples. \\ 11.2 x 106 = Steam flow from both OTSG's at 100% full power. If only one OTSG is being used to cool the RCS, this value becomes 5.6 x 106 lbs./hr. NOTE: One OTSG can be used to cool RCS. This must be determined and only the sample from the active OTSG utilized. t EM-305 Rev. 0 4 p,q, 30 nk.sg.gs:!,wr,-sw;&Na-a m+yse a :k x v-_ W & 6 *c a +x ~ !!523 "" K l' T .~ ' ~ - _, ~ - r- ,.t s.
pym~;'3d ;3 ~ 'hx. T'.' ~ ' ' d' (h Vs = Specific volume of steam 28,317 = Conversion of cubic feet to "cc". 1 = Conversion of hours to seconds 3600 T = Duration of release in seconds FPT = Percent full power at time of trip in decimal form To convert uCi to Ci, multiply by 1 x 10-6, 5.3 TOTAL CURTEM RFT.FICED FROM STEAM prf.FasE 5.3.1 Determine the total release of radionuclides in the steam using the following formula: Total Ci Noble Gas + Total Ci Radiciodines = AT Q 5.3.2 Report the results of this calculation to ChemRad Supervision V and the Emergency Coordinator. Record the results on Enclosure 2. S.4 dicroDS nrr.r1CE EVALUATION FROM TURBINE BUILDING VENTILATION 5.4.1 As directed by Chemistry Supervision and/or the Emergency Coordinator, obtain a gaseous grab sample of the Turbine j Building atmosphere in an appropriate gas beaker. 5.4.2 Analyze per CH-230, Gamma Spectroscopy Utilizing the ND-6685. 5.4.3 Record activity concentration on Enclosure 2. 5.4.4 Determine and record on Enclosure 2 the exhaust rate of the Turbine Building ventilation system (cubic feet per minute). v EM-305 Rev. Page 31 KGG;!;.h-%wygn ' e,~.- cj'ypi. :r:. e a. -:-QW.}!7*}T~};+.
}.
'.~ l 1~G_,3l f
.g3 y _ :..,,. s, g - .y-y. .1 ;-n.:z m:~~M -a, s. ..w -+w T r.-w>.+rm,. <= nn can: - n e i~.L:;. ' 1. .a. i .a.,. s 5.4.5 Complete the calculation of Turbine Building vent releases on. 5.4.6 Report results of this calculation to ChesRad Supervision and the Energency Coordinator. 6.0 IEOTIFIc1?TMC 6.1 All data accumulated per this procedure is to be summarized on and 15 and forwarded to the Emergency Coordinator via Chemistry Supervision. 6.2 Personnel leaving the General Assembly ' Area for the purpose of sampling the effluent releases per this procedure are to be listed on Enclosure-3 which is to be forwarded to the Emergency Coordina-tor. EM-305 Rev. 0 4 l-page 32 (;rp-3gwm w,a==... .a usa n.
- -~'t- -.w.r w c :.p :.v..-~
=- a
- .u.L' C, ~.: ~ ~: = = :
- > kd.V :,.,,, ". uy:::1.,. . :s-a.,
- w.
_.._~;_--=._.- ~ e 7.0 ENCLOSURES s_.- 7.1 Enclosure No. 1 Fig. 1-3, Access Route to Sample Station 7.2 Enclosure No. 2 Data / Calculation Sheets 7.3 Enclosure No. 3 Post-Accident Sampling and Analysis of Effluent Releases from the Plant, Emergency Coordinator Notification 7.4 Enclosure No. 4 Reactor Building Vent System Indicator Light Status (LMHVC) 7.5 Enclosure No. 5 Auxiliary Building Vent System Indicator Light Status (LMHVC) 7.6 Enclosure No. 6 Handle for Cartridge Clamp 7.7 Enclosure No. 7 Part. Iod. Sampler Assembly 7.8 Enclosure No. 8 Cartridge Extractor Assembly 7.9 Enclosure No. 9 Filter Cartridge Clamp Within Sampler 7.10 Enclosure No. 10 Reactor Building Vent Range ) 7.11 Enclosure No. 11 Aux. Building Vent Range 7.12 Enclosure No. 12 Vent AIMS Manifold 7.13 Enclosure No. 13 Sampling Equipment Check List 7.14 Enclosure tio. 14 Gaseous Effluents Dat'a Sheet 7.15 Enclosure No. 15 Minimum Sample Flush Times f3 \\ ) v EM-305 Rev.0 4 Page 33 ' G.."_{7TW::s &Q4, +.&;ikisn W.' ? Q M1P P DhW ".Y'I*'N:T ~~Du ~. f *~ .:_T:.'
a y e.. %i;- ^ .c -~ F ' ' .w % ~. _._._ ,[j " ~ ,nk':4 r m _t.>:;~., -~ ~ 48 ENCLOSURE i (Figure 1 of 3) [?, gyp) [gy /gy v l4 ,.r. ae m 4 's w ---.--uce ((.1 a i -- i a 4 t h i -- i i -- i C ] } c m J L W DJ I!E J
- cy g d t
j ,.. i Ld ') 'o .- [p{ oo t.- ) p i 1 x' L .J c oo 9 seri "[ im 8 -g .e im 0 1[ 1 0 i -I m ces I -I ,a g. q g! ) [ b h g a o @ O!m& @l n D ,a u \\ EM-305 RevQ 4 j Page 34 , in a..;w;..~..;.t ? .m i._.. ~~". _rr--- - a v.nu.s < 2..,... s:en-r
C.;.. + au--
- ' ~_.;.,:,
_ aa .. ~ _ n,,.n... ._._n_._,;_._._.._ s u f E ENCLOSURE 1 (Figure 2 of 3) g s..- i -W I L hi i s Q wi!*) h = so.;Or Il o l
- Ii!
...............i................ $ .............a- .................g 3 ;t l l .:= O $0 i hl s is 1 5 b' i 5 L f' J f e1-h q H E iin e__ I~D bE s hI l!* 00 L lc-f. 119 i!'p G io n 7' niin!HiiinlHlu f a i i l 1 I r O'O-O)i-i ( i lO l 1 2 \\ ) m..- EM-305 Rev. 0 4 Page 35 ] ' b' j, f. A tEIR' y 9 6
. +.,, n :< - : ic2? y l s n... . b h_% n,_..a ...n-~- r~'" ' ' u
- ,is.
9. ENCLOSURE 1 (Figuro 3 ef 3) ise ne m.wm sea cause IllillllIIIII = 1I111 O s (nL') g HtMilttit-25 O' OO \\ E -e z -,m_z e n -. a ~ M V 2* W = O U cC ~ \\ ~ewu s. s N N N i n$. E N d N 5 a a n I tu . r w% ~ 1 1 wt R. C
== v fc5 5 4 E_ N = s l 6 I 5, = = = = L-s s= i = = .;;;in L te.! L +. 5 i g. Ms
- "(3 1"l tultui o g
^ gg ~,- 3 d pn,
- 4 z
g <g 0 O~ O~ v l dp* ~- ) m ^
== == S e 25 Zs 9., a is -g a w EM-305 Rev0 4 ray. x e.s - M4 m ~ ^, ' J * '. }h[ E=' ' _'. 4/ 8,' '.n3* ! *55' v..I yN,I,'*A(p 'E).p e ,91. t.N% *) *[ .,t [r h,h 4,.- *; * [' 'g-;e, 'I ~ i
- Q?., :.;:
_~ i.h d. _ - a : R;,,__, ~ & 4 ~ 4*&..
- l
^ 4 e ENCLOSURE 2 ,._x (' ) (Page 1 of 6) V 1 DATA / PAT-CULATION SHEET Date/ Time I.- NOBLE CAR RFTfARE EVALUATION FROM STEAM RELEAST \\ 1. Utilize this section only if: / t a. Unit did not experience loss of off site s power, or loss of condenser vacuum, or loss of bypass steam. (And) b. RM-A12 did not indicate a significant and sustained count rate increase (factor of 10 or better), or failure, or spurious high alTras. (g Last RM-A12 Noble Gas Sample (Total): \\ l Ci/cc \\ FP at Time of Trip: \\ \\ FP at Time of Last RM-A12 Sample: \\' (*If not known, input 100%) L Duration of Release: sec. Total Curies of Noble Gas Released: curies Initials 2. Utilize this section only if: Date/ Time a. Unit did not experience a loss of off-site / power, or loss of condenser vacuum, or loss of bypass steam. (And) lV EM-305 Rev.0 4 page 37 T'),M37* pf>f+, z'i Na tw ~ 9,p --wtegipw K ~ ' ~ .-.7 ~ l~ - usw; y,. = ~ - ~ ...r
i d., 6.+ -
_ _w; _ vb . ~; e - c... ENCLOSURE _,2 (Page 2 of 6) %J b. RM-A12 indicates a substantial increase in count rate (). 10 times normal), or failure or spurious high alarms. \\ FP at Time of Trip: \\ Duration of Release: sec. RM-A12 Sample Result (Total): uCi/cc Total Curies of Noble Gas Released: curies Initials 3. Utilize this section only if: Date/ Time a. Unit experienced loss of off site power or / ~ / s loss of condenser vacuum, or loss of bypass i .J ~- steam. OTSG Shell Side Sample (highest activity): uci/cc Main Steam Temperature: 'F Main Steam Pressure: psia Specific Volume of Steam: cu.ft./lb. t FP at Time of Trip: \\ Duration of Release: sec. Total Curies of Noble Gas Released curies Initials (~T r V EM-305 Rev. 0 4 page 38 w.:..: - ~ ~ ~ ' ~}'Tf-Q" np, '-x 2 q o
- ik;..~~1
u...;.. *.. 2.: ;.~.vm. !-w,.'.. : _ a. n. -.O ~ ui,?..n'~.' '*.,. 2: D A. '...'...x,. * '. '... '- W - Li
- .c._, a.
..n- ' ~..- :Xa' ~ e b ENCLOSURE 2 / \\ Q (Page 3 of 6) II. RADI0 IODINE EVALUATION FROM STEAM RrtrisE Date/ Time 1. Utilize this section only if: / a. Unit did not experience loss of off site power, or loss of condenser vacuum, or loss of bypass steam. (And) b. RM-A12 did not indicate a significant or sustained increase in count rate (factor of 10 or more), or failure, or spurious high alarms. Last Main Steam Resin Sample (highest activity): uCi/cc Duration of Release: sec. t FP at Time of Sample: \\' (*If percent full power is not known, input 151) t FP at Time of trip: \\ Main Steam Temperature: 'F Main Steam Pressure: psia f 1 j Specific Volume of Steam: cu.ft./lb. Duration of Release: sec. Total Curies of Radiciodines Released: curies Initials O EM-305 Rev.0 4 pay, 33 7%%f
- -~'5 M
- 2 2 2 h_f ' 2 9:-
2:W&-- ~'r ? ~
r6'. . [d$, s ' _. ias.,, ~ ; lE -- ',,- ~..,... ,....,, '.~.,_..'. e.1
- .ne :- *.--ip,,. ',,.,,}*..,, j -
J.~ ENCLOSURE 2 (Page 4 of 6) Date/ Time t 2. Utilize this section only if: / a. Unit experienced loss of off site power or loss of condenser vacuum, or loss of bypass steam. (.QI) b. RM-A12 indicated a substantial increase in count rate () 10 times normal) or failure or spurious high alarms. OTSG Shell Side Sample (highest activity): uCi/cc Main Steam Temperature: 'F Main Steam Pressure: psia Specific Volume of Steam: cu.ft./lb. t FP Prior to Trip: Time of Release: sec. Total Curies of Radiciodines Released: curies Initials i l i C tN EM-305 Rev.0 4 page 40 W
- d
[# * ......w,..'*8* !* '. *
- P
~ f 'b" ^ ~. ' ' * ^ m:= +
W:.;:p [ ??," -} " '~~,l C " ' }.- K - _} ..J._, im ENCLOSURE 2 (Page 5 of 6) III. TOTAL CURIES RFtFARED FROM STEAM RELEASE Date/Titne Total Curies of Noble Gas (from I): / curies i + Total Curies of Radioiodine (from II): curies Curies Released (Total): Initials l l l DATA RECEIVED BY TITLE l DATE/ TIME / l O IV. CASE 00S RTLFASE EVALUATION FROM TURBINE BUILDING Date /Tirtie VENTILATION Gaseous Activity (Total) (A): uCi/cc / Turbine Building Vent Exhaust Rate (F):
- 1. 2 x 106 cfm A X 28,317 x F x 1/60 =
_ uCi/sec. WHERE: 28,317 = Conversion from cfm to cc. 1/60 = Number of minutes in 1 sec. Initials DATA RECEIVED BY TITLE DATE/ TIME / O 'EM-305 Rev. Page 41
- EQ5+h ii34 Gp*Ne xab GGA:t re-,_ _ -r&na:t -_.-
~"%:AO:- < Jc*L. u -' ' ' ^= K t ~ _.- - ?-: e ~.
k : $ i d, [ ; '. ,,,,,.,,[.,.';,, h ,, f,,_ 9 =5kN$ N5. ,.yl, A'.,..c .'.[kh.' ~,dMtM k.',)...y..: ./ m\\ ENCLOSURE 2 Q (Page 6 of 6) Date/ Time Remarks of Methodology Not Utilized for Data Reduction: / (List all data obtained and calculations made to evalu-ate releases). (vD Initials DATA RECEIVED BY TITLE DATE/ TIME / C i EM-305 Rev.0 4 page 42 wv..s, a F T P T., %,r,- t;.pp;C,rne.= w.v.e;. ,s.w _a v a Envmm,c:.s, -n 1 .n 's
r@- i ci.,.. ..xWp, 1 ..,.-..f$ s e c.3.W:6,fr;., -. r4.--- : _, _ ',-gj.. ._ _ g,, . _ j-7f _ ,-S DCLOSURE 3 %./ POST-ACCIDENT SAMPLING AND ANALYSIS OF EFFLUENT RELEASES FROM THE PLANT, EMERGENCY COORDINATOR NOTIFICATION
- List of personnel performing Sample Acquisition:
Name Title 1. 2. 3. 4. 5. Date/ Time of Entry (projection): / G'b ' Working Copy
- of EM-305 available.
Initials
- To be completed prior to leaving the General Assembly Area for the purpose of sampling effluent releases under EM-305.
O r 3 'wJ EM-305 Rev.0 4 page 43 -l.GUTF. win-Jga:-,.w;i.;> ach. e.w t :c7.isw3 2: wr wysts<mc9 ;T.._u 4 ~ c.1. .g ~
..a __w!p.;,vam_Q.u,,;.:... n g. w w. r.-. w -c = ;m.;_-:s. Mu.., w -=y.,...__+.,...g,m:,-.- ..? y:.k..., a r:9 7 n. .,, [ [_ n ,r;e, e f3 ENCLOSURE 4 REACTOR BUILDING VENT STSTEM INDICATOR LICH7 STATUS Indicator Light t1 t2 t3 t4 t5 t6 t7 t8 t9 t10 RMV-003 l ON M RMV-004 ON ON ON ON ON H RMV-005 ON ON P A RMV-006 ON ON N E RMV-008 ON ON ON ON ON ON L RMV-009 ON l RMV-025 ON ON ON ON t1 System Initialization, Low Range ( t2 Low Range and Mid Range v t3 Mid Range and High Range, Low Range Flushing t4 Mid Range and High Range t5 High Range, Mid Range Flushing t6 High Range Only t7 Mid and High Range t8 Mid and High Range t9 Low Range Only t10 Low Range Only, same as t1 1 ,O EM-305 Rev. 0 4 page 44 ,;,_gi.e.w w -.=.w+ w.;.,x .w +4 w p m,-_...w nn wt,s ..mcvyejD ~sa - .7=~~~~,.. - _ __... = _n_ _- a- ~ .e.
" J-W. - -M.fk.h thdsjv.
- 6 $tv.x _ A'r
.Th'i,w -_ g.- ...,.,, _. '- ' C;d" ~ ~ o, e [^s ENCLOSURE 5 I (J AUYILIARY BUILDING VENT SYSTEM INDICATOR LIGHT STATUS Indicator Light t1 t2 t3 t4 t5 t6 t7 t8 t9 t10 RMV-015 ON RMV-016 ON ON ON ON ON RMV-017 ON ON RHV-018 ON ON RMV-020 ON ON ON ON ON ON RMV-021 ON RMV-026 ON ON ON ON t1 System Initialization, Low Range h t2 Low Range and Mid Range (d t3 Mid Range and High Range, Low Range Flushing t4 Mid Range and High Range t5 High Range, Mid Range Flushing t6 High Range' Only t7 Mid and High Range t8 Mid and High Range t9 Low Range Only t10 Low Range Only, same as t1 A \\ (G EM-305 Rev.0 4 page 45 5_TiX%=.; = ;- a:n a., 9;m wna;;;m t a-t!%adyn -? 7:..:-:- __. 27+~.., -- c-[*~~ '~ T' l ~ _ - _, __+ -. _, -
,s
- 3..c :,g,...,
4: .. w e-- ..-s..,.:,.+.-:_ z_ n. c,w, c. -,.3 ,, r _ _. -~e~; 1 1 ENCLOSURE 6 [N O) b 1 % C s,) ,, q ( \\ 8 e b Cartridge clamp :Icadle / / o / s / / s EM-305 Rev. 0 4 p,, 4s (E;-;sgp.r:5w;+vaq+W-strww.%g:::n.=ua. ='rn.ngy-c.a.:-e%%usim+ +-+ n;;;p ~~ qx : :-~
. m ig.M.G1.h' '
- _ C; ;._' _..,, :
a_, '.,v.. < ;..y N4 s 7 '4
- a :q <.".* h.,_
.., 3 u .,,.,..r. b + <>v- ,7, .2 e y / ') ENCLOSURE 7 Q i v ~ h s g e y 4 4 1 .#,r ,f ) IN x l N l [i is N i b. I s a j d i 1 es I I e i, N / l i L __ A. m l-j I Particul ate & N d I %~- F Cha: coa 1 Holder ', s a _f l Ml p hi i .- g l .) g s { h .z. (3 ~% Y (d / s s m s = b Y / / / / / //////s, s y1 lr ~ Sampler Assembly es Particulate Iodine U EM-305 Rev. 0 4 p,,, 47 i I j yMg{F '{ 73 7 7 --- F T'W 3 N - ' ',ggi. .M 9'
- Lf u-_C.*l'wif 2t
-4w 4,l'eQ __ ,.,.f' ) g
n.u. s.:.. . u a u.- .w.. q;..<.n" '... s. e.?, ..:s. ~. -
- %,~ :,. tp:.e -z,,.
<. y e ;..~.e- : + ;n; g.1.uw:n. - w. g. ..-..'...a P- / ENCLOSURE 8 r ( i x / m. I l e M N l l s /~% (. t e 6 e / Ca ndge..sceablv f f Extractor i /% %.) EM-305 Rev.Q 4 j Page 48 lM*%2Xnw \\*- -u.y .n-r.e : - -m sp-' t ~w -u -, c. - - u-sw- .ui v.,: - ~ -
- Z A n *^^ :., x
+'s + .a- .e.. .*.a a
._z- . a__ :. : - .s,,<
- .,=:. :
, a r-- - e a-4-- .e -'-:4., -.q.s.v, J tf?f. m ;t e. s _ -- ~e=- zu. 3.;,..'. N ENCLOSURE 9 I ) \\v! ) v rFt r l J l l<l N hd Nb /m \\. N i li i
- 'j
\\ l \\. I C. -] x_ ,a D I ~( *i ( '> I c u s su AM\\W\\\\WM\\.W\\\\' A\\Ww\\MNwS\\N I O swsw m \\ww w w w w W ws\\w wws e: v Particulate Charcor.1 Assembly /Ca:.tridcTe Clamo l '8 i ) \\_/ EM-305 Rev.0 4 Page 49 .Ii 1 $" #*s k. b d W Y*T ? .'E .**.e N
c. ,,w,.. . ~ ~y_.s. y;n. .,.;pn., .u, ..n p ., ;. ? L,.,+'-. ': s~- :.
- ;;..; 5 u__.. ;, -- --
+a.. 4 c p ENCLOSURE 10 m)N 'r A [ "d ? GR l 2 -4 E R C g ? w! c me <0 o e, me
- e e w-a ao
<o EU in t. I A J t J =I 4 1 7 m k I 9
- .a b
m I. u F'y = 1 ,r w N h 'f um emi b Q l 'l* (T os 'J L 2 r% a n x 4 0 3 3 o i r-e 3 o o +- =% m t. M % -4 m EG m , 15 + (,a- ,u h 8 p 6 w ss e o Se ? V/ S l n m 1;,5 k 5 In l P 4 1 n U t. '4 EM-305 t Rev. 0 4 Page 50 CT[~iYl2.'%fs.'h&iiW "t t"Lc= *We h-= ' ~'" h?.%K.TN.C.4W - u'- N'5Ts- 'h"*4 #5'N'A '* * 'Ni'NG ' *- ~ ' WD N' 5 Y ~- $ ~~ - -
+.-G :.i..
- ;ei. f......,. a.. -L l 5 W,,._
[i].'=--!..:.'. _,..ht [ _z,____; \\ N $8f ENCLOSURE 11 ( V ) > a.
- a. O -
e
- a E
.C' f ) 4=0 L \\ 4 w g ~l < l 3 f v = = es I h 4 4' E y m-g' :- y 3 3-k = t Vse3 on a 5 b*4 NT e \\ 5 4 J-lh[--g a;. ..e t_g { YE f 2 7 -k 5 ,3 3 4 n. p O 2 e P= a 0 -4 .o =
- ' 3 M
M i ) -4 .i n]f M. 3 b Il yt u t ( "" m = Sep Td-e b, \\h as 3 o u u h h l ) 7 tv 1 t -LJ 9 9 m in .t r a a M p =4 % \\/ e P O, r + EM-305 Rev.O 4 ease si jIl}tMjbyf:-D.~ M' ^+f>:^-{:QH1]s4&Q$$.% T54.%s %;.l.: ' i' U'.*,. ~ -
'$q j"1 g M J 'i re w.<<- e "j 2 t><1 C><l-M4-j V W5 'O W5v-55 WSV-56 *SV' N wsV93 o,y g g .? . d$ RI.rn, Detec,koR. -D4-N i f ui c,4a w,vis f PM&uloj > 7'? r d' j! 1; L ws ?# v ta 7, If h h ) j CSn(), SimphT. wsv Cl g-3 e- . ~/, };S r, y c L J j, L.. Ll2
- y y, ap, rm g/ -
w ar to id 'l 7 1 o e wsvJ7 i., hear ren4.- 5 [: $W $ To AC$ Y u sv *)O 'O E # * $ U 14 f T ~ .'j b (wev43 f BI i f A. t y f** /15' h$ s, wsv-6 t wsytr wsvce vsv&7 . 9 1 m$ t r.
- # ' 7 A.I fD., TEhIOC
,h g 11 i: in 3 M i R i-Grab Sampler and A.I.M. Detector k ; [ { o A I..< ) t: Note: With WSV-71 and WSV-72 turned a fl[ h j ' re.. em.ng fully clockwise, flow is thru g I, f g,y.,, the By-pass line. 1;. A { M rden Am AZ l Omy g
.g_v ..;wi-a -~. ag3;==- x-- :-- LLg5.r. ;- ;-. w;;4 ' :- - :- ~ 2.; p: L_2,- - :: w v.: -. :s:.m u.n :., a. ac m. ; ;. ?.. d.sa y :--..i 1 1 " u ~...v :.=. -:-v z gy:2 ;,. - :,.,,.... .c
- m ENCLOSURE 13 POST ACCIDENT SAMPLING KIT CHECKLIST (143' ELEV.)
Quantity 1113 (Minimum) 1 Extension Rod 1 Tong Extractor Assembly 4 Filter Canister Containing Silver Xeolite cartridge and glass fiber filter wrapped in air-tight bag 1 Speed wrench for AIMS NEAR LINE ISOLATION 1 Shielded carrying container 1 Adjustable Wrench 1 Grab Sampler Transit Cover 2 Plastic Bags \\ EM-305 Rev.6 4 Page 53 ?.4a+7p.= r;yg+, r g g 7l3 yggtrer,<r-gyzge v6Hym;5 f,-y.pw - __ _.ue
- v. s3. e-nnw : s ~2, .., e.:eua>.::..m i.vm ~ >g+.:. v--u,w~< : sn.~. n. ;m:;m.. Pr.%.s :. ,.:+ _ >.x :. a.- + w &s,a : :. s... u...... :x.~ l \\ / ENCLOSURE 14 O} f MMEOUS EFFLUENTS DATA SHEET DATE: TIME: AINS ANALYSIS Samnle Point: Reactor Building Atmosphere Reactor Building vent Auxiliary Building Vent ReDort Tvoe Flowing Sample Summary Report (CMSUMR) Flowing Sample MDA Report (CMMDA) Flowing Sample EBAR Report (CMEBAR) Flowing Sample Iodine Report (CMIEQ) (% ( 4 Standard GSP Short Report (GSSRPT) %/ Standard GSP Long Report (GSLRPT) Standard GSP MDA Report (GSLLD) Total Activity (uCi/cc) from report, if applicable Major contributing isotopes from res, ort, if applicable uCi/ce, uCi/ce, uCi/ce, uCi/cc-l uCi/ce, uCi/ce, uCi/ce, uCi/cc uCi/ce, uCi/ce, uCi/ce, uCi/cc I SIGNATURE / TITLE a EM-305 Rev.0 4 page s4 6r:n.~.wwr.= _wa.g p g m n w m. :a e.n-.:- m.e = ~:
+ ~l._',. L.: i-l: "'.?;;,,,, ll1,, _; y :.l,^,;. _,'.,. '%. y._., , l.. G,!?}y; ';,m..nh.%~u- .. -.. w, l -. S 9 ENCLOSURE 15 v Min i miin Samole Flush Times Reactor Building Vent 1 minute Auxiliary Building Vent 1 minute O I \\ l 4 EM-305 Rev. Page 55 (LAST PAGE) t l l ,'?,,_ .,J"- j * '!I 'bE$. N. N t CYsNM Nf8 I(2*8CUth k- [dVsM'[6YN3b?db-'t j SOA45*d N ? h4/h,5Nd ge' f b = s,
- q. -..: i. + ;A y g.: :;; ten:1;'sp :..>...~ :... 7' y L g.2.::g ;-
e / ~' Rev. 27 11/19/86 V (HKC 12/29/86) COCUmO?!!Seh[,.,; [ N F O R ;qf3 7 j a g: 9..gg~ y/ C S. f D':L-3 T j EMERGENCY PLAN IMPLEMENTING PROCEDURE EM-202 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DUTIES OF THE EMERGENCY COORDINATOR O THIS PROCEDURE ADDRESSES NON-SAFETY RELATED COMPONENTS l REVIEWED BY: Plant Review Committee / // / Date 11/19/86 Meeting No. 86-46 APPROVED BY: Dir., Nuclear Plant Operations l E -l Y h b $ L _. - /, ~lNi? / Date //l9 9 <fl~ h / / INTERPRETATION CONTACT: Nuclear Safety Supervisor i I
+,- M -:,pg W Y:.2+@: '. n. n; ' p.g e.< 1 0 1 1.0 SCOPE ,o 1 r 1.1 PURPOSE This procedure provides instructions and guidelines to be utilized by the Energency Coordinator during initiation of the Radiological Emergency Response Plan. Specific guidelines include energency classification, reporting, and notification requirements, and recommended protective actions for gaseous plume exposures. 1.2 DISCUSSION 1.2.1 (Classification of Postulated Accidents) provides a listing of postulated accidents at CR-3 for which specific physical indications and Emergency Action Levels have been identified to expedite emergency classification. These postu-lated accidents have been categt zed ur.de-the following a conditions: Accident condition Location in Enclosure 1 a. Personnel Injury Page 1, Item la b. Radiation / Contamination Pages 1-3, Items 2a-k c. Natural Phenomena Pages 3-4, Items 3a-g d. Man-Made Phenomena Pages 4-5, Items 4a-e e. Luss of Control Functions Pages 5-6, Items Sa-i l27 f. Loss of Power Pages 6-7, Items 6a-c l g. Core Damage Pages 7-8, Items 7a-f h. Loss-of-Coolant Accident (LOCA) Page 8, Item 8a-e 1. Secondary Systems Pages 8-9, Items 9a-d
- j. Miscellaneous Page 9, Items 10a-d O
EM-202 Rev.g 7., Page 1
' ~ e :nc<.g gr. W P:EmnWW. m n.n: wm T.ba -- = v.w e.x. m .e ~ (j 1.2.2 In order to correlate the basis for this Plan with the accidents evaluated in the Final Safety Analysis Report (FSAR), has been prepared to provide a sumary listing of example conditions for determining the emergency classifica-tion. Although it is impossible to provide an all-inclusive listing of examples, these are included to provide sufficient guidance to the Emergency Coordinator in making a determination of emergsacy classification. Quantifiable measures will be utilized to classify the incident by its potential consequences i rather than its causes. In this regard, it is noted that many of the incidents tabulated may be classified in more than one category, depending on their potential consequences. 1.2.3 provides guidance for determining the appropriate j25 protective measures to be taken within the Crystal River j Generating Complex. Its purpose is to integrate consideration j O' of quantitative plant data, site physical characteristics, and j meteorlogical data when making a decision to shelter or j evacuate personnel. l 1.3 AUTHORITY 1.3.1 Based on the evaluation of the emergency condition, the Emergency Coordinator has the authority to implement the following actions. direct any or all personnel to shelter or evacuate the l25 Crystal River Generating Complex l order any or all Crystal River Generating Complex Plants to be placed in a safe shutdown condition noti fy all applicable agencies of the status of the nuclear plant request outside assistance, if necessary make decisions related to classification of the emergency condition EM-202 Rev. p Page 2 I A
- . ?p.:.
.x c~ :o. c .. w a _w._.. ( ) make decisions rel ated to noti fication and recomen-a dations for protective actions to State and Local authorities responsible for off site emergency measures until the Emergency Operations Facility (EOF) Di rector assumes this responsibility. NOTE: The EOF Director normally assumes the res pons-ibility for noti fication and protective action recommendations when the' designated State and Local authorities arrive at the EOF and establish communications with their respective agencies. make the necessary personnel assignments to provide for r~s {) continuing res ponse and su pport for l ong-term activities. 1.4 DEFINITIONS 1.4.1 Onusual Event This classification covers two major areas: any event ( s) in process or having occurred which indicate a ptential degra-dation of the level of safety of the plant; and any prsonnel inoy that is complicated by contamination or radiation r exposure requiring transportation to an off-site hospital. The " Unusual Event" classification is designed to bring the oper-ating staff to a state of readiness in the event of escalation to a more severe action level classification. ,r 3 U EM-202 Rev g 7 Page 3 - =-
g. v-p;.;w www.~.v: vr '. ca:a :-: - w: = ' ~n ' w %..:..:._'.w .: =. 1.4.2 AlcIt f3 This classification refers to an event (s) that are in process or have occurred which involve an actual or potentially sub-stantial degradation of the level of safety of the plant. The " Alert" classification includes emergency situations which are not expected to threaten the public, but for which it is deemed prudent to alert the off-site emergency organizations. 1.4.3 site Area Eneraency This classification refers to an event (s) that are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. This classification is very likely to involve some radiation exposure to the public. 1.4.4 General Enercency This classification refers to an event (s) that are in process or have occurred which involve actual or imminent substantial core degradation or nuclear fuel melting with potential for loss of containment integrity. It also includes other acci-dents that have large radioactive release potential. This is the most severe classification of emergency and some protective actions will be recommended by the Emergency Coordinator. l27 1.4.5 Esercency Coordinator Energency Coordinator is the position with which the highest level of authority for on site energency activities resides. This position will be held by the Director, Nuclear plant Operations or his designated alternate, the Man-On-Call. lO l EM-202 Rev2 7 Page 4
1 .c ; v.c.y. m 3.gr.ra,,;3 HKC 06/20/86 fm I ) (/ 1.4.6 Actina Emeraency coordinator Acting Energency Coordinator is a pro-temp position held by the on shift Nuclear Shift Supervisor and has the authority of the Energency Coordinator until relieved by the designated Energency Coordinator. 2.0 PRECAUTIONS 2.1 Complete understanding of the accident, as well as the degree of implementation, is mandatory before relief of the acting Energency Coordinator can be carried out. 2.2 During exercises, drills, or tests, ALL MESSAGES shall begin and end with 'THIS IS A DRILL
- or 'THIS IS AN EXERCISE' 2.3 In any case where a ' General Energency' has been declared, the miaisua protective action recommendation shall be: " Evacuate all people within a 2 mile radius and shelter all people 5 miles in the potentially affected sectors."
2.4 Consideration should be given, when making protective action recommendations to Generating Complex personnel, that there is only one suitable evacuation route from the site (main access road). Increased shelter time or early evacuation may be required under certain radiological or meteorological conditions. 3.0 RESPONSIBILITIES I 3.1 The Energency Coordinator is responsible for the direction of all activities - at the plant site during an activation of the Radiological Energency Response Plan. The position of Energency Coordinator is assumed by the Director, Nuclear plant Operations, or the Man-On-Call, or may be temporarily filled by the Duty Shift Supervisor during off-hours. EM-202 Rev.Q 7 Page 5 1 [
..n.- w~ ..x.c :.:. :w : w.., - ~~. a.,,... wws ~., w.: : mv,..w c. 3.2 The Emergency Coordinator is res ponsible to provide the Emergency / Recovery Director an incident re port which must document the emergency and serve as a basis for recovery o perations. This report should consist of the actual scenario of the emergency, and the identified cause or causes. The radiological history of the emergency will also be detennined, such as released quantities, existing radiological ac tivity levels, etc. NOTE: Information substantiating the sequence of events 'during the emergency condition shoul d be compiled from communication
- logs, ta pe recordings, fli p
- charts, message copies, photographs (if available) and other pertinent documentations.
3.3 The Emeroency Coordinator is responsible to the EOF Director. 3.4 During declared emergencies, the Emergency Coordinator will be the sole contact for emergency regulatory directives and will evaluate these directives for possible response to the emer-gency i.ondition. 3.5 The Emergency Coordinator shall not delegate the responsibility for decisions rel ated to classi fication of the emergency condition. O EM-202 Rev.2 7 j Page 6
....,,_..-c.. v. r.. t..
- n. s.o y.
.,...g y. (s) 3.6 The Emergency Coordinator shall not delegate the responsibility for making decisions rel ating to noti fication and recommen-dations for protective actions to State and Local authorities responsible for off site emergency measures. However, at the time the E0F is declared manned and operational and State Re presentatives are present, the E0F Di rector shall assume responsibility for these actions.
4.0 REFERENCES
4.1 Radiological Emergency Response Plan 4.2 Emergency Plan Implementing Procedures (EM-200 Series), Volume III of the Plant Operating Quality Assurance Manual (P0QAM) 4.3 CP-111, Documenting, Re porting, and Reviewing Noncon forming p Operations Reports 5.0 EQUIPMENT 5.1 Emergency Coordinator's Manual 6.0 RECORDS AND NOTIFICATIONS 6.1 All signi ficant in formation, ev'ents, and action taken during the emergency period should be recorded and retained for later evaluation. This in formation is compiled from fli p charts, tape recordings, message copies, photographs (i f available), logs, etc. EM-202 Rev.2 7 Page 7 _.-._.,_..-____w__--
%::.. 4 ng.;j:. ,, _u..;,n_. ..s r e HKC 06/20/86 I I V' 6.2 Notifications must be made in accordance with the instructions of this procedure. These notifications should be made by an individual appointed by the Energency Coordinator. 6.3 Utilize the time blocks in Sections 7.1, 7.2, 7.3, and 7.4 to provide a reference to verify actions taken and for later reference during accident reconstruction. 7.0 INSTRUCTIONS 7.0.1 The Energency Coordinator shall initiate the Radiological Emer-gency Response Plan in accordance with this procedure. Specific guidance for each emergency classification is given in this procedure in the following Sections: 7.1 Energency Coordinator's Guide for " Unusual Event" 7.2 Emergency Coordinator's Guide for ' Alert' 7.3 Emergency Coordinator's Guide for " Site Area Emergency" 7.4 Emergency Coordinator's Guide for " General Emergency" 7.0.2, Classification of Postulated Accidents, should be used in determining the energency classification. 7.0.3 When the Director, Nuclear Plant Operations or his designated alternate arrives on-site, he must contact the acting Energency Coordinator and receive a briefing relative to the current status of the accident and implementation of the Radcological Emergency Response plan. When ready to assume responsibility as Energency Coordinator, the
- Director, Nuclear Plant Operations aust inform the acting Energency Coordinator that he has assumed this responsibility.
EM-202 Rev.2 7 Page '8 a.~,, - _,. na-
.n l L. s.... -@ a+.. ' wxm., x.; , c
- 1.,.em - r _....._na.z
- _... _ _ e..
4 7.0.4 Telephone notifications of emergencies, including emergency l 's_,, tests or drills to the NRC (Nuclear Regulatory Commission) and other off-site agencies, are not considered complete until direct voice contacts are made with the responsible represen-tatives of the agencies being notified. The leaving of a message with an agency's tolephone
- operator, secretary, answering service, or message recording device is not con-sidered a completed notification.
NOTE: When making the initial notification of an emergency l27 condition to the NRC and the State Warning Point, l Tallahassee (SWPT), the highest emergency classification l level that would have applied at any time prior to the l call should first be declared. The classification can j then be downgraded to a lower level at the time of the l fm call, if conditions warrant. l C/ 7.0.5 For the initial notification of an emergency condition to tne State Warning Point, Tallahassee (SWPT), a separate verifica-tion contact is required prior to transmission of the notifica-tion. When conducting notifications with the SWPT, the following steps will occur: CR-3 will make contact with the SWPT utilizing the State Ring Down phone, NAWAS, commercial phone circuits or Local Go'vernment Radio - when the communications link is established with SWPT Duty Officer, the person making the notification will state: "This is Crystal River 3. This is/is not c drill. I have a message". At this point the SWPT Duty Officer will acknowledge and r'~N ask the person to wait EM-202 Rev. g 7 Page 9 -- - ~en
, x33p,.. ' ~. esy,.n r:.%.~ 7 :;.r n.- w.n rg. _.y.:.
- 3.,,
'N The Duty Officer will then contact the CR-3 Control Room ,/ using an outside phone line to verify that CR-3 is in an emergency condition and a message is being sent. Upon verification, the Duty Officer will then perform a station roll call (OHRS, Levy County EOC, Citrus County E0C) When roll call is complete, the Duty Officer will then instruct CR-3 to state his message. The message is given and then repeated in its entirity to ensure that eacn organization notified is fully cognizant of the contents of the emergency message. Before terminating the transmission, the person making j?S the notification will state: "This is Crystal River 3. j 7 ( _) This is/is not a drill. End of mes:iage." l 7.0.6 In order to assure that each agency or organization notified of an emergency condition at CR-3, each message will be repeated in its entirety. p. ( ) 1 -l EM-202 Rev.2 7 Page -10 l t .-=.-=.-a==r. .. - -=--
6-;.XLi.C.D;; AK*MWWWTM..D f) Q 7.1 EMERGENCY COORDINATOR'S GUIDE FOR " UNUSUAL EVENT" NOTE: TO ENSURE RAPID RESPONSE TO EMERGENCY CONDITIONS, MANY OF THE STEPS LISTED SHOULD BE PERFORMED IN PARALLEL BY DELEGATION OF RESPONSIBILITIES. Time 7.1.1 Unusual Event Declared NOTE: Noti fication of the State Warning Point is reouired within 15 minutes of classification. 7.1.2 Notify CR-3 plant personnel: If a local evacuation is reouired, sound the appropriate 25 alarm (i.e., RB, Auxiliary Building Evacuation) if applicable. Notify plant personnel via PA system of the type of emergency, emergency classification, location, and areas 25 to be avoided (as applicable). Repeat the announcement. Establish continuous monitoring on PL-1. Resound the alarm. 7.1.3 Notify Chem-Rad with details and reouest they assess the Radiological ascects of the situation and report findinns to the Emergency Coordinator. O EM-207-Rev2 7 Page 11 ---a. -.-~,n_n_,,.,,,___n_,:_. .-.,n,,--.
. e d A g p a n c.;.0 5.".n y,s a $ / e. s M d 9 e ->t.. ? O n s e d rb.i: w ee d y. - S.1 : 7-m_,._..._,_....... j f Time O'" 7.1.4 Notify the Director, Nuclear Plant operations or Man-On-Call l27 as soon as practicable. (Refer to EM-206, call List III) 7.1.5 Notify the EOF Director as soon as practicable. (Refer to EM-206, call List II) 7.1.6 Augment on-shift resources: Assess resources (manpower and saterial) If necessary, activate appropriate Emergency Teams: Medical Emergency Team j27 Radiation Emergency Team Plant Fire Brigade Environmental Survey Team - Refer to EM-206 Sampling Team Emergency Repair Team Dose Assessment Tean Obtain emergency services from B&W if required. (Refer to EM-206, Call List II) 7.1.7 Complete the STATE OF FLORIDA NOTIFICATION MESSAGi. (Enclosure 2). 7.1.8 WITHIN 15 MINUTES of declaration of an Unusual Event, notify the State Warning Point via one of the following communica-tions network (numbered in order of priority): (1) State Hct Ringdown (Station 22) (2) NAWAS (1st alternate) bG EM-202 Rev.2 7 Page 12
m p m.w g r, w..%. pegg,- HKC 08/14/86 (3) Commercial Telephone (904-488-1320 or 904-488-5757) Time (4) Local Government Radio and relay information from Notification Message Form (Step 7.1.7). 7.1.9 Notify the Unit 1 & 2 Control Room and the Unit 4 & 5 Control Room that an Unusual Event emergency classification has been declared at Unit 3. (Refer to Enclosure 5.) 7.1.10 Complete the NRC Event Notification Worksheet in accordance with 10 CFR 50.72, (Notification to NRC is required as soon as practicable but must be made within 1 hour of classification) on Enclosure 3. 7.1.11 WITHIN 1 HOUR of declaration of Unusual Event, notify NRC via j one of the following: (1) Emergency Notification System (ENS) (2) Commercial Telephone alternates: 1-301-951-0550, ( d 1-301-427-4056, 1-301-427-4259, 1-301-427-8893 and relay information from the NRC Event Notification Work-sheet (Step 7.1.10). 7.1.12 Continue to assess plant conditions and; Establish Conaunications Restrict access to the area if required. Establish " stay times' as necessary. (Refer to Enclosure 4) i Interrogate personnel to assist in the reconstruction and evaluation of the emergency. Keep plant personnel informed. 7.1.13 If plant conditions change, review the Classification of Postulated Acciderts Table (Enclosure 1). EM-202 Revg 7 Page 13 _... ~ ~., ~. .._...,m.,.
- ,m
,,-__m__
mmm d HKC 06/20/86
- D(V Time 7.1.14 If upgrading Energency Class, proceed to step:
ALERT - Step 7.2 SITE AREA EMERGENCY - Step 7.3 GENERAL EMERGENCY - Step 7.4 7.1.15 Provide periodic plant status updates or provide updates when plant conditions change but energency class remains Unusual Event. Provide updates to: Director, Nuclear Plact Operations or Man-On-Call (Refer to EM-206, Call List III) (At regular intervals or upon request) EOF Director (Refer to EM-206, call List II) (At regular intervals or upon request) State Warning Point (At least every 1/2 hour) NRC (At least every hour) 7.1.16 If terminating Unusual Event, notify:
- Director, Nuclear Plant Operations or Man-On-Call (Refer to EM-206, Call List III)
EOF Director (refer to EM-206, Call List II) State Warning Point with verbal summary NRC with a verbal summary Units 1 & 2 Control Room and Units 4 & 5 Control Room. .7.1.17 Assure follow-up actions are taken in accordance with appro-priate Emergency and Abnormal procedures. O EM-202 Rev.2 7 Page .14 ( 7h&W ' ' 9 3 s ** %%O4C 9*MJrE Kr st /M*2Ti#d@aNhMW" * "-'" '- t ih -- ' ~Z~
~..m ,., c,., y _.-w.. .y i, . n,,, , ~. I J Time s.- 7.2 EMERGEk'.Y C00ROINATOR'S GUIDE FOR " ALERT" NOTE: TO ENSURE RAPID RESPONSE TO EMERGENCY CONDITIONS, MANY OF STEPS LISTED SHOULD BE PERFORMED IN PARALLEL BY DELEGATION OF RESPONSIBILITIES. 7.2.1 ALERT declared. NOTE: Noti fication to the State Warning Point is required within 15 minutes of classification. 7.2.2 Notify CR-3 p1 ant personnel: 77 (,) If a local evacuation is required, sound the appropriate j25 alarm. (i.e., RB, Auxiliary Building Evacuation) Notify plant personnel via PA system of the type of j25 emergency, emergency classification, location, and areas to be avoided (as applicable). Direct all personnel not j actively involved in combatting the emergency to report to their designated Assembly Area as per EM-205. Repeat the announcement. Establish continuous monitoring on PL-1. Resound the alarm. / t l ~., EM-202 Rev.2 7 3 Page 15 a em~-mm m
7 z ..a..g. m.m _ u.... Time 7.2.3 Notify Chen-Rad with details and request they assess the Radiological aspects of the situation and report findings to the Energency Coordinator. 7.2.4 Notify the Director, Nuclear Plant Operations or Man-On-Call as soon as practicable. (Refer to EM-206, Call List III) 7.2.5 Notify the EOF Director as soon as practicable. Refer to EM-206, call List II) Request an " Alert" of the Corporate Emergency Support Organization. 7.2.6 Augment on-shift resources: Assess resources (manpower and material) If necessary, activate appropriate Emergency Teams: Medical Energency Team l27 Radiation Emergency Team Plant Fire Brigade Environmental Survey Team - Refer to EM-206 Sampling Team Emergency Repair Team Dose Assessment Tean Obtain emergency services from B&W if required (Refer to EM-206, call List II) 7.2.7 If a radiological release has occurred due to the emergency, assign an individual to complete EM-204(A). (Data will be used in the State Notification Form, Step 7.2.8) 7.2.8 Complete the STATE OF FLORIDA NOTIFICATION MESSAGE FORM (Enclosure 2). O EM-202 Rev.2 7 Page 16 ~.- ~ =. = -, m_,
w - r-e e,o.,- m -- -- ...~ 7 HKC 08/14/86 Time iV 7.2.9 WITHIN 15 MINUTES of declaration of an Alert notify the State Warning Point via one of the following communication networks (numbered in order of priority) (1) State Hot Ringdown (Station 22) (2) NAWAS (1st alternate) (3) Commercial Telephone (904-488-1320 or 904-488-5757) (4J Local Government Radio and relay information from Notification Message Form (Step 7.2.8). 7.2.10 Direct an individual to activate the TSC and OSC. (Refer to EM-206, call Lists III & IV) 7.2.11 Notify Units 1 & 2 Control Room and Units 4 & 5 Control Room that an Alert emergency classification has been declared at Unit 3. (Refer to Enclosure 5) 7.2.12 Notify the Corporate Security Specialist that an Alert has b been declared. (EM-206, Call List V) 7.2.13 Complete the NRC Event Notification Worksheet in accordance with 10 CFR 50.72, (Notification to NRC is required as soon as practicable but must be made within 1 hour of classification) on Enclosure 3. ~ 7.2.14 WITHIN 1 HOUR of declaration of Alert notify NRC via one of the following: (1) " Emergency Notification System (ENS) (2) Commercial Telephone alternates: 1-301-951-0550, 1-301-427-4056, 1-301-427-4259, 1-301-427-8893 and relay information from the NRC Event Notification Worksheet (Step 7.2.13) A EM-202 Rev.2 7 Page .17 un.uw ~.wwwa,vmmmaeam. -~ m: -' : --- - - -~
.,. ;G y........, ..w.~_.,.. .g. -. _ w. HKC 06/20/86 V Time 7.2.15 Continue to assess plant conditions and; . Establish Conaunications Restrict access to the area if required. Establish " stay times' as necessary. (Refer to Enclosure 4) Interrogate personnel to assist in the reconetruction and evaluation of the energency. Keep plant personnel informed. Consider assembly of non-essential personnel from other Generating Complex areas that are downwind of a potential release. (Refer to Enclosure 4, 5, and 6) 7.2.16 Notify American Nuclear Insurers (Ref er to EM-206, Call List O -g 1 V II) 7.2.17 Notify FPC Risk Management (Refer to EM-206, call List II) 7.2.18 If plant conditions change, review the Classification of Postulated Accidents Table (Enclosure 1) 7.2.19 If upgrading Emergency Class, proceed to step: SITE AREA EMERGENCY - 7.3 GENERAL EMERGENCY - 7.4 7.2.20 Provide periodic plant status updates or provide updates when plant conditions change but emergency class remains Alert. Provide updates to: Director, Nuclear Plant Operations or Man-On-Call (Refer to EM-206, Call List III) (At regular intervals or upon request) OV EM-202 Rev g 7 Page 18 ...-u.-+.n -. m- - = - n- - -- -
- , t ;,e
.... 5 _ n.e., v -~.. '. v:-- -- - -:^~~
- - - W. ~
.,. u - L.. _ :._. HKC 06/20/86 /,h l v Time EOF Director (Refer to EM-206, Call List II) (At regular intervals or upon request) State Warning Point (at least every 1/2 hour) NRC (at least every hour) 7.2.21 If terminating Alert or de-escalating to Unusual Event notify:
- Director, Nuclear Plant Operations or Man-On-Call (Refer to EM-206, Call List III)
EOF Dig,ector (Refer to EM-206, Call List II) State Warning Point with verbal summary, followed by a written summary within a hours. NRC with a verbal summary, followed by a written summary within 8 hours. Unit 1 and 2 Control Room and Unit 4 and 5 Control Room Corporate Security Specialist (EM-206, Call List V) 7.2.22 Assure follow-up actions are taken in accordance with appropriate Emergency and Abnormal Procedures.. C EM-202 Rev.M 7 Page 19
- MP8'%E*Na M
- MINA. - -
m.,.s -v/4 *M' t """*- x .s-c-.D.*?W "?....a 5.T.? '7. *M*" */ '*W.N * *** *.. "I' ' 7.***.~ ~ ** " " ~ ~ * " "
.. ~ .<.7; - . x x,., g.;,w ~s,;- ~x s .) 7.3 EMERGENCY C00RDINATOR'S GUIDE FOR " SITE AREA EMERGENCY" NOTE: TO ENSURE RAPID RESPONSE TO EMERGENCY CONDITIONS, MANY OF STEPS LISTED SHOULO BE PERFORMED IN PARALLEL BY DELEGATION OF RESPONSIBILITIES. 7.3.1 SITE AREA EMERGENCY declared. NOTE: Noti fication to the _ State Warning Point is required within 15 minutes of classification. 7.3.2 Designate the Administration Building or Receiving Warehouse l2E as the Main Assembly Area. l 7.3.3 Noti #y CR-3 plan .sonnel: l , - ~ ( ,) Sound Site Evacuation alarm. Notify pl ant personnel via PA system of the type of l25 emergency, emergency classification, location, and areas to be avoided (as applicable). Direct all non-essential l personnel to proceed to the Main Astembly Area. Speci fy l the location that has been designated as the Main Assembly l Area (Step 7.3.2). l Repeat the announcement. Establish continuous monitoring on PL-1. Resound the alarm. 7.3.4 Notify Chem-Rad with details and request they assess the Radiological aspects of the si tuation. Dispatch the appropriate Emergency Teams as required: ps, ../ EM-202 Rev.g 7 Page 20
u p.c 6c,s.-m :V. y,i -;y_. :.,:- 1.-:+y,, : y gwsW2: Time - /N Q Medical Emergency Team 27 Radiation Emergency Team Plant Fire Brigade Environmental Survey Team - Refer to EM-206 Sampling Team Emergency Repair Team Dose Assessment Team 7.3.5 Notify the Director, Nuclear Plant Operations or Man-On-Call as soon as practicable. (Refer to EM-206, Call List III) 7.3.6 Notify the EOF Director as soon as practicable. (Refer to EM-206, call List II) Request activation of the Corporate Emergency Support Plan. 7.3.7 Augment resources: Assess resources (manpower and material) If necessary, activate additional personnel to augment the Emergency Teams. (Refer to EM-206, Enclosure I) Obtain Emergency Services from B&W if required. (Refer to EM-206, Call List II) 7.3.8 If initial off-site dose assessment has not been recorded, assign an individual to complete EM-204( A). (Data will be used in the State Notification Form, Step 7.3.9) 7.3.9 Complete the STATE OF FLORIDA NOTIFICATION MESSAGE FORM. (Enclosure 2) 7.3.10 Determine the appropriate protective actions to be taken within the Crystal River Generating Complex. (Refer to.) Provide instructions concerning assembly or evacuation to the Nuclear Security and Corporate Security organizations. (Refer to EM-206, Call Lists III and V) O EM-202 Rev. 2 7 Page 21 ... - ~ - - - - - ~ l
3.:::.m y a wp- ; c c :n p;s.,> s(. ,...e ] j -~. Time V) t 7.3.11 WITHIN 15 MINUTES of declaration of a Site Area Emergency, notify the State Warning Point via one of the following communication networks (numbered in order of priority). (1) State Hot Ringdown (Station 22) (2) NAWAS (1st alternate) (3) Commercial Telephone (904-488-1320 or 904-488-5757) (4) Local Government Radio and relay information from Notification Message Form (Step 7.3.9) 7.3.12 Lirect an individual to activate the TSC and OSC. (Refer to EM-206, Call Lists III & IV) 7.3.13 Notify other Generating Complex Units that a Site Area Emer-gency has been declared and direct them to
- assemble" for roll
(- call or evacuate all non-essential personnel as per the l27 Crystal River Coal Plant Site Accountability / Evacuation l Manual. (Refer to Enclosure 5 and EM-206, Call List V) l 7.3.14 Notify the Energy Control Center of the emergency conditions at CR-3 and the need for power in the 10 mile Emergency Planning Zone around CR-3. The lack of electrical power in this area would defeat the Early Warning N"otification System sirens, which are the primary method for alerting the public in the event of an emergency. 7.3.15 Ensure plant security has implemented EM-211, " Duties of the CR-3 Security Organization. " Personnel accountability SHALL be verified within 30 minutes of Site Evacuation. O EM-202 Rev.M 7 Page 22
- 3. - - % m q w w.s. g r,,-- - ?.i,-;;-(.- 7.- v ; 7;----
g z ] g-g = 2._
- f. ;
Time 7.3.16 Complete the NRC Event Notification Worksheet in accordance with 10 CFR 50.72, (Notification to NRC is required as soon as practicable but must be made within 1 hour of classification) on Enclosure 3. l 7.3.17 WITHIN 1 HOUR of declaration of a Site Area Emergency, notify the NRC via one of the following: (1) Energency Notification System (ENS) (2) Commercial Telephone alternates: 1-301-951-0550, 1-301-427-4056, 1-301-427-4259, 1-301-427-8893 and relay' information from the NRC Event' Notification Work-sheet (Step 7.3.16) 7.3.18 Continue to assess plant conditions and; Establish Consunications ' C l Restrict access to the area if required. Establish " stay times" as necessary. (Refer to Enclosure 1 4) l27 Review on-site protective actions and verify that non-1 essential personnel downwind of the plume are, or are assembling or evacuating as appropriate. Consider shutdown and evacuation of Control Roon personnel of other Generating Complex operating plants affected. (Refer to Enclosure 4 and 5) Interrogate personnel to assist in the reconstruction and evaluation of the emergency. Keep plant and other Generating Complex personnel informed. (v EM-202 Rev. g 7 Page 23
.. ~ -.. . ~.. N HKC 06/20/86 Time 7.3.10 Notify American Nuclear Insurers (Refer to EM-206, Call List II) 7.3.20 Notify FPC Risk Management (Refer to EM-206, Call List II) 7.3.21 When EOF is operational, transfer responsibilities to the EOF Director for Protective Action Recommendations and Notifications to the State. 7.3.22 If plant conditions change, review the Classification of Postulated Accidents Table. (Enclosure I) 7.3.23 If upgrading Classification from Site Area to General Emergency, proceed to Step 7.4. 7.3.24 Provide periodic plant status updates or provide updates when plant conditions change but emergency class remains Site Area ( ) 'u - Emergency. Include meteorological assessment and, if any significant off-site releases are occurring, dose estimates for actual release. Provide updates to: Director, Nuclear Plant Operations or Man-On-Call (Refer to EM-206, Call List III) (at regular interval:: or upon request) EOF and CCC when activated. (At regular intervals or upon request) State Warning Point (At least every 1/2 hour until EOF Director has assumed this responsibility) NRC (At least every hour) Unit I and 2 Control Room and Unit 4 and S Control Room (,) 't.) EM-202 Rev. g 7 Page 24 _ _ _ ~ -, _ _ -.. _ _ _ ~ _ _.... _.. -.. _ _ _ _ ~ _ -
' s~ - ". ;t -n. _,_ 3 _ 3. v.- --_ ::,9,..( 7.; <.
- 2.. -y:ya. r::.
7.3.25 Close out or de-escalate the emergency class by coordinating efforts with the State, MRC, and EOF Director. Provide a written summary to off-site authorities within 8 hours of closecut or de-escalation. NOTE: If the EOF is operational, the EOF Director in conjunc-l27 tion with the Energency Coordinator is responsible for l the decision to closecut or de-escalate the energency. 7.3.26 Notify Units 1 & 2 Control Room and Units 4 & 5 Control Room. 7.3.27 Assure follow-up actions are taken in accordance with appro-priate Energency and Abnormal Procedures, A. l l l \\ EM-202 Rev.g 7 Page 25
' Tip ' F -- :$~: ~;* _: 4 :. ~.2: - L _.u ~; -^~ . >.,. v.,rs...-:x. t,:.cy,s u'. h Time tV) i 7.4 EMERGENCY COORDINATOR'S GUIDE FOR " GENERAL EMERGENCY" NOTE: TO ENSURE RAPID RESPONSE TO EMERGENCY CONDITIONS, MANY OF STEPS LISTED SHOULD BE PERFORMED IN PARALLEL BY DELEGATION OF RESPONSIBILITIES. 7.4.1 GENERAL EMERGENCY declared. NOTE: Notification to the State Warning Point is required within 15 minutes of classification. 7.4.2 Designate the Administration Building or Receiving Warehouse as the Main Assembly Area. 7.4.3 Notify CR-3 plant personnel: Sound Site Evacuation alarm. Notify plant personnel via PA system of the type of emer-gency, emergency classification, location, and areas to be ' avoided (as applicable). Direct all non-essential personnel to proceed to the Main Assembly Area. Specify the location that has been designated as the Main Assembly 'rea (Step 7.4.2). A l Establish continuous monitoring on PL-1. Resound the alarm, i I EM-202 Rev.M 7 Page 26
.~ m- .,mg - --t Time ,m 7.4.4 Notify Chen-Rad with details and request they assess the Radiological aspects of the situation. Dispatch the appropri-ate Emergency Teams as required: 27 Medical Emergency Team Radiation Emergency Team Plant Fire Brigade Environmental Survey Team - Refer to EM-206 Sampling Team Emergency Repair Team Dose Assessment Team 7.4.5 Notify the Director, Nuclear Plant Operations or Man-On-Call as soon as practicable. (Refer to EM-206, Call List III) 7.4.6 Notify the EOF Director as soon as practicable. (Refer to f)J EM-206, call List II.) Request activation of the Corporate Emergency Support plan. 7.4.7 Augment resources: Assess resources (eanpower and material) -If necessary, activate additional personnel to augment the Emergency Teams. (Refer to EM-206, Enclosure I) Obtain Emergency Services from B&W if required. (Refer to EM-206, Call List II)~ 7.4.8 If initial off-site dose assessment has not been recorded, assign an individual to complete EM-204( A). (Data will be used in the State Notification Form, Step 7.4.10) 7.4.9 Determine the appropriate sequence for evacuating non-essen-tial personnel from the Generating Complex. (Refer to. ) provide instructions concerning evacuation to the Nuclear and Corporate Security organizations. (Refer to EM-206, Call Lists III and V) EM-202 Revg 7 ] Page 27 - _, _ u,.-- e.- m-
. *3.;p. ;... :r%y, .4 : m:mi.a;p_.. c a.7~;,:: q*m ".*. v. :.- Q- ~:., w ~ - Time 7.4.10 Complete the STATE OF FLORIDA NOTIFICATION MESSAGE FORM (Enclosure 2) 32II: MININUM PROTECTIVE ACTIONS I.QR GENERAL EMERGENCY SHALL BE: 2 MILE, 360 DEGREE PRECAUTIONARY EVACUATION 5 MILE SHELTER OF POTENTIALLY EFFECTED SECTORS (Refer to Enclosure 4 for further protective actions) 7.4.11 WITHIN 15 MINUTES of declaration of a General F.mergency notify the State Warning Point via one of the following communication networks. (Numbered in order of priority) (1) State Hot Ringdown (Station 22) tO (2) NAWAS (1st alternate) (3) Commercial Telephone (904-488-1320 or 904-488-5757) (4) Local Government Radio and relay infornation from Notification Message For:n (Step 7.4.10) 7.4.12 Direct an individual to activate the TSC and OSC. (Refer to EM-206, Call Lists III & IV) 7.4.13 Notify other Generating Complex Units that a General Emergency has been declared and direct them to " assemble" all non-essen-tial personnel, perform accountability, and prepare for poss-ible evacuation as per Enclosure 6 and the Crystal River Coal l27 Plant Site Accountability / Evacuation Manual. (Refer to l and EM-206, Call List V) d EM-202 Rev. 27 Page 28
a. . --. vrmy. .~ i.., w;w;y-.g-gn ;,.. 3-- _3. e HKC 08/14/86 Time V 7.4.14 Notify the Energy Control Center of the energency conditions at CR-3 acd the need for power in the 10 mile Emergency planning Zone around CR.3 and also of the possibility of a request for the safe shutdown of Units at the Complex. The lack of electrical power in this area would defeat the Early Warning Notification System sirens, which are the primary method o'f alerting the public in the event of an emergency. 7.4.15 Ensure plant security has implemented EM-211, " Duties of the CR-3 Security Organization". personnel accountability SHALL be verified within 30 minutes of Site Evacuation. 7.4.16 Complete the NRC Event Notification Worksheet in accordance with 10 CFR 50.72, (Notification to NRC is required as soon as practicable but must be made within 1 hour of classification) n l (V on Enclosure 3. 7.4.17 WITHIN 1 HOUR of declaration of a General Emergency, notify the NRC via one of the following: (1) Energency Notification System (ENS) (2) Commercial Telephone alternates: 1-301-951-0550, 1-301-427-4056, 1-301-427-4259, 1-301-427-8893 and relay information from the NRC Event Notification Worksheet (Step 7.4.16) 7.4.18 Continue to assess plant conditions and; Establish Communications Restrict access to the area if required. t E.4-202 Rev. g 7 page 29
3..
- s.s m - ;. '
- ,cW.3;.. V ""] 1 %g,Q:+-D-RiRi- % 2.W ;
- 'Y 'i - G,
- L :.,.f. :- - ' K;;- - -l.----
~ g Time U) I Establish
- stay times" as necessary.
(Refer to Enclosure 4) Verify non-essential personnel downwind of the plume are, or are being evacuated. Consider shutdown and evacuation of control Roon personnel of other Generating Complex operating plants affected. (Refer to Enclosure 5) Interrogate personnel to assist in the reconstruction and evaluation of the emergency. Keep plant and other Generating Complex personnel informed. 7.4.18.1 Notify the designated Florida Power Recombiner Procurement l26 Representative to initiate bringing hydrogen recombiners on l site with the required personnel to operate them. (Refer to l EM-206, call List II). l 7.4.19 Notify American Nuclear Insurers (Refer to EM-206, Call List II) 7.4.20 Notify FPC Risk Management (Refer to EM-206, call List II) 7.4.21 When EOF is operational, transfer responsibilities to the EOF Director for Protective Action Recommendations and Notifica-tions to the State. 7.4.22 If plant conditions change, review the Classification of Postulated Accidents Table (Enclosure 1) 7.4.23 Provide periodic plant status updates or provide updates when plant conditions change but energency class remains General Emergency. Include meteorological assessment and, if any significant off-site releases are occurring, dose estimates for actual release. s EM-202 Rev.2 7 ~ Page 30
p . ' );.<;.;6-q'7+:.q : ^. ~, :; C.py;n ' ::' %..t;. W W." v;. Q:.e [.-;.sht ;fsl. ' .._.,_ u. Time 7 Provide updates to: Director, Nuclear Plant Operations or Man-On-Call (Refer to EM-206, call List III) (At regular intervals or upon request) EOF and CCC when activated. (At regular intervals or upon request) State Warning Point (at least every 1/2 hour) until the EOF Director has assumed this responsibility. NRC (At least every hour) Unit 1 and 2 control Room and Unit 4 and 5 Control Room. 7.4.24 Close out or de-escalate the emergency class by coordinating efforts with the State, NRC, and EOF Director. Provide a written summary to off-site authorities within 8 hours of closecut or de-escalation. \\ NOTE: If the EOF is operational, the EOF Director in conjunc-l27 tion with the Emergency Coordinator is responsible for l the decision to closecut or de-escalate the emergency. a 7.4.25 Notify Units 1 & 2 and Units 4 & 5 Control Room. 7.4.26 Assure follow-up actions are taken in accordance with appro-priate Energency and Abnormal Procedures. 8.0 ENCLOSURES Classification of Postulated Accidents State of Florida Notification Message Form NRC Event Notification Worksheet Guidelines for Recommended Protective Actions for Gaseous i Plume Exposure Information Sheet for Emergency Notification of On-Site FPC Organizations On-Site Protective Actions d I i EM-202 Rev. 2 7 Page 31
V: I [^ * ( V rs ?- ~r CIASSIFICAT'ON OF POSTMATED AOCIDDffS i .7 C0f0ITION INDICATIONS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY PROC. REF. l 3
- 1. PERSHAEL IKREY
$;I e h $4 EM-202 c. Transportation of con-N/A X EM-213 3 taminated injured individ-t ual from site to off ite hospital. f" EM-202 EM-204(A) l'i
- 2. RADIATICII/00BffAMINATICII EM-204(B) a.
Tech. Spec. Noble Gas-RM-Al and/or RM-A2 X X l27 ,.) es instantaneous release (Warning alarm at (1t 10 times interlock at 100 times EM-210 rate limit exceeded. of limit interlock actuation point. Interlock actu-EM-305
- .6 27 fg actuation at 10% of (1 Tech. Spec.
ation setpoint. 7 [.p limit.) limit.) (10 times Tech. Spr.c. limit.) EM-208 s AP-240 l27 [34 2 X EM-202 d.l
- b. Effluent monitors and/
RM-Al and/or RM-A2 EM-204(A) y) or portable devices detect and/or portable EM-204(B) [i dose rates corresponding monitors and air l27 to 250 aren/hr. whole samples. EM-210 body, or 1.25 res/hr. 27 thyroid at the 4400 ft. ji exclusion area boundary. EM-208 AP-240 l27 f >.) t i l' mcInsimE 1 (Page 1 of 9) Page 32 EM-202 Rev.p 7 l t
f O O O W p 'O CIASSIFIC& TION OF POS11NATED AOCIDGrf5 k; L: %e 00lOITION INDICATIONS LNElSUAL EVENT ALERT SITE AREA DGERGENCY GDIERAL EMERGENCY PROC. REF. c. Effluent monitors and/or RM-Al and/or WA2 Dt-202 9 EM-204(A) portable devices detect and/or portable 1:vels at the 4400 f t. ex-monitors and air EM-204(B) s-clusion area boundary samples. l27 7 Dt-210 e >50 aren/hr. for 1/2 hour or 27 1, >500 aren/hr. d ole body for L 2 minutes (or 5 times these EM-208 [ 1;vels to the thyroid). Ut-305 AP-240 l27 !ll., d. Projected dose rates at Portable monitors X EM-202 Dt-204(A) the 4400 it. exclusion area and/or calculation. Dt-204(B) b boundary correspond to 11 ren/hr. whole body or 15 l27 Dt-210 h ren/hr. thyroid, under De-208 2 actual meterological C.a conditions. f,f 27 o. Sustained and Uneval-RM-A1 through RM-A8 X s uated airborne radioactiv-and/or W All through a ity concentration exceed-RM-A15. ing radiation monitor a alarm limits. f.P-240 2-EM-208 l.' EM-202 1 {, f. Removable surface con-Survey X Dt-208 EM-202 tamination (p,v) outside 2 g l RCA 12200 dps/100 cm, 2 averaged over a 100 ft I area EM-208 q. Removable surface con-Survey X EM-202 tamination(agoutsideRCA 150 dps/100 an, averaged over a 100 ft2 I area. r EN'IDSURE 1 (Page 2 of 9) Page 33 Rev k. s EM-202 e i
). CLASSIFICATI0ft OF i ATED ACCIDENTS ^ * 'JONDITION INDICATIONS UNUSUAL EVENT ALERT SITE AREA EMEGENCY GENERAL EMSGENCY PRM.REF. h. Unexplained direct ra-RM-G1 through RM-G18 X X diction level increase ex-(>100 times (>1000 times EM-202 ceeding radiation monitor normal) normal) EM-208
- (
f alar 7 limits. 3 I
- i. Containment Gross X
X X X AP-380 l27 ,4 l C2mata monitor Reading ex-RM-G29 >10 R/hr. >100 R/hr. >1000 R/hr.plus 2 >10,000 R/hr.plus EM-202 m i ceeding limit. (Via Con-RM-G30 of the following: 2 of the follow-EM-208 f trcl Room Instrumentation.)
- 1. RCS pressure ing:
l27 >1500 psig.
- 1. RCS pressure
- 2. Containment
>1500 psig. q h pressure
- 2. Containment g
>4 psig. pressure >30 j
- 3. Containment psig.
4 temperature
- 3. Containment
[ >180*F. temperature ,a >200*F. j
- j. High coolant activity RM-L1 and/or sample.
X X EM-202 requiring shutdown per >1.0 uCi/gm. 1300 uci/gm. AP-270 l27 l Technical Specification Dose equivalent Dose equiv-3/4 4.8. 1-131 or, >100/E alent 1-131. l uCi/gm for 48 hours. k. Other conditions exist, High radiation and/ X Applicable frm whatever source, that or contamination ems. 61 I make release of large levels. k amounts of radioactivity in a short time period possi- {l ble. f' 3. NA'lVRAL PHEN (9ENA t { ~ a. Ihtrricane Warning NAWAS, MIT tower X X X AP-1076 l-Instantaneous Sustained Wind EM-202 wind speed speed >300 mph., 1300 mph. with unit not in l G21d_aluitdown. b. Earthquake being ex-Seismic monitors X X AP-961 perienced or projected. activate. Any earthquake. Any earth < puke EM-202 causing seismic monitor annun-ciator alarm. l EtrIDSURE 1 (Page 3 of 9) Hev. h g. Page 14 EM-202
n lh p. ( O Q_) CIASSIFIC&TIcel 0F POSTUIATED AOCIDDrFS ColOITION INDICATIONS UlWSUAL E\\" Q!' AI.ERT SITE AREA EMERGENCY GENERAL DIERGENCY PROC. PE.F. j
- c. Tornado being experi-NAWAS, visual X
X AP-1076 g enced. Nearby that could Strikes EM-202 potentially strike facility. H .k facility.
- d. Fire Visual, fire X
X X EM-216 alarm (>10 minutes dur-potentially Compromising the AP-880 ation) affecting function of safety-EM-202 .? safety-related related system. I systems (>10 (Inability to shut minutes dur-down the unit or f.) ation.) extinquish fire.1 n. Flood being experienced NAWAS, Intake Canal X X X AP-1076 ij or projected. level. At levels 198.0 At levels At levels 1129.0 ft EM-202 ft. but (129.0 ft. 1129.0 ft. with unit not in d cold shutdown. k ff f. Missile Impact. Visual, noise. X X AP-1076 From any source Affecting plant EM-202 ij on the facility operations with hj severe damage to j5 safe shutdown [.: equionent. g. Severe natural phenom-NAWAS, visual. X Applicable procedures enon being experienced or projected with plant not in cold shutdown. 4. IRN-MADE PEDHEMA a. Severe explosion. Visual, noise. X X X EM-202 t l Near or on-site Affecting plant Affecting plant but not af fecting operations but operations with i plant operations. rio severe dam-severe damage to age to safe safe shutdown shutdown equip-equipment. ment. [NCII)SURE 1 (Page 4 of 9) {; Page 3S EM-202 Rev. g 7
0 7 f N (/ f b. CIASSIFICATION OF POSTUIATED AOCIDENTS ? '.i j C0f0ITION INDICATIONS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY PROC. REF. EM-202 h b. Toxic or fla==ahle gas Odor, breathing X X X in the envircoment at difficulty, explo-Near or on-site Entry into fa-Entry into vital AP-513 l27 1 k life threatening levels, sion, etc. but not entering cility not areas. facility. affecting vital Li areas. c. Aircraft crash or un-Visual, noise. X X X EM-202 I usual aircraft activity On-site, but not Hitting the Hitting vital over facility. hitting the facility. areas with unit "( facility. not in cold shut-down. f; d. Security threat. Visual X X X X Security j Att;empted entry or ongoing Imminent loss of Ioss of physical Procedures h) attempted sabotage security control of fa-control of fa-EM-202 [*: compromise. cilitv. cilitv. e. Train derailment on-Visual X sits affecting access or l containing hazardous material. d 5. IDSS OF 00NfBOL 'i EUNCTIONS [: a. Ioss of cold shutdown Ioss of heat sinks, X AP-380 l;j capability. e.g.,DIR and OTSGS. EP-260 EP-290 ix EM-202 id 'b. Ioss of hot shutdown RCS temperature,RCS X EM-202 D f( capability, pressure, flux level, etc. c. Failure of RPS to in-Rod positions, RCS X X AP-580 itiate and complete a temperature, RCS No core damage Core damage or EP-140 i' Reactor Trip which brings pressure, flux immediately likely core melt EM-202 f Reactor subscritical. level, etc. evident. [ (Both manual or automatic) s l Ett'IOSURE 1 (Page 5 of 9) EM-202 Rev. g 7 Page 36 f
i [ CIASSIFICATICII OF = ATED ACCIDENTS HKC 9/86 h ^ 8 j CONDITION INDICATIONS UNUSUAL EVENT ALERT SITE AREA DGRGENCY GENERAL EMERGENCY PROC. REF. d. Evacuation of M1in X X AP-990 Control Room Local control No local control AP-240' fr established. 115 minutes. AP-513 7 EM-202 EM-208 c. Ioss of containment Isolation valves, X AP-1061 integrity requiring shut-equipment hatch, air EM-202 s down. lock. f. Ioss of ESF or fire X protection systems requir-ino shutdown. g. All alarms lost. All annunciator X X { windows u d computer 1 15 minutes with EM-202 ~ alarms inoperable. plant transient a h. Ioss of alarms or indi-Appropriate X b ) l cations for process or component alarm. EM-202 ] effluent parameters requir-1 ina plant shutdown.
- i. Significant loss of Loss of prisary and X
EM-202 assessment or communications secondary MET data or AP-240 / capability (e.g., all MET or M1 RMS instrumenta-AP-270 h FMS instrumentation). tion 6. IDSS OF POWER [/ l p t a. Ioss of of fsite power loss of feeder X X AP-530 pf OR all on-site AC power. breakers, loss of 115 minutes AP-580 y: Control Room light-AP-770 ~ ing, loss of RC pumps. etc. EM-202 i b. Ioss of offsite power loss of feeder X X X AP-380 AND all on-site AC power. breakers, loss of .(15 minutes >15 minutes No EFW >3 hours. AP-530 f I' Control Room light-AP-580 ing, loss of RC AP-770 pumps, etc. EP-260 i-EP-290 EM-202 t DK'IDSIIRE 1 (Page 6 of 9) s I EM-202 Rev. 2 7 Page 37 j,
o m. ] v i i CIASSIFIC& TION OF POSTt4ATED AOCIDDirS HKC 12/29/86 Y J.f 00EITION INDICATIONS UNUSUAL EVENT ALERT SITE AREA DERGENCY GENERAL DERGENCY PROC. REF. [ ,a c. Ioss of all on-site Diesel start, loss X X AP-580 y DC power. of feeder breakers, .{15 minutes >15 minutes AP-380 7 etc. De-202 "h E 7. 00RE DMEE AP-270 g' a. Reactor Coolant Pump RC pump trip, RM-L1 X AP-530 l failure, leading to fuel alarm, RCS pressure, AP-580 failure. RCS temperature, in-AP-380 core thermocouples, Dt-307 [j NI Error, Tsatmeter, Dt-202 ej SPWs. etc. p b. Degraded core with Incore thermocouples X pt-307 Q possible loss of coolable RM-L1 alarm, Tsat AP-270 geometry. meter, NI Error, EP-260 p. SPIOs, etc. EP-290 j De-202 c '~ c. Inss of fuel cladding. RM-L1 alarm, sample X X Dt-307 i i Sample indicates Sample indi-EP-260 j jl: >0.1% failed fuel cates >11 EP-290 in 30 minutes. failed fuel in EM-202 ,y f 30 minutes or AP-270 >St total fuel of; failure. F d. Irradiated fuel damage RM-G15 through X X X accident in Reactor Build-RM-G18, RM-G29, No release of Limited damage Major fuel damage gf ' ing or Auxiliary Building. RM-G30, RMA-Al radioactivity. with release or water below AP-240 through RM-A4 and of radioac-fuel level. EM-308 l_ RM-A6. tivit v. Dt-202 e. Core melt likely. Incore thermocouples X Dt-202 Tsat meter, SPNDs, EP-260 In etc. EP-290 l- {> P ENCIDSURE 1 (Page 7 of 9) EM-202 Rev. g 7 Page 18
'R O O c')- s, v 1.: rTrMIFICATICII 0F POSTUL&TED AOCIDDrrS 85 hl COM)1 TION INDICATIONS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY PROC. REF. '5/ 4 X EP-390 M f. Ioss of 2 of 3 fission RM-L1, RC pressure, EP-2% R product barriers with a RC temperature, Tsat EP-290 G potcntial loss of 3rd. meter, SPNDs, etc. EM-307
- i (o.g., loss of primary EM-202 j
coolant boundary, clad AP-270 l27 failure, and high potential [ for loss of containment. 9 8. IDC& N AP-380 a. RCS Code Safety or PORV VPIs, Tail piece X EM-202 1.,t stuck open. temps, RCS pressure, Ij RCI7F level, pressur-F. izer level. b. Reactor Coolant leak. RC pressure, pres-X X X X AP-380 surizer level, RB >1 gpa unident- >50 gpa >1000 gpa With ECCS failure EM-202 I sump level, RB itied leakage. and subsequent failure of Con-O. temperature, RB tainment heat re-R.i pressure. noval system )3 y hours. AP-380 7 c. EECS initiation (valid Diesels start, HPI, X EM-202 (( actuationl. RB isolation. d. Steam generator tube RM 425 through X X X EP-390 l27 [ leak. RM-G28 and RM-A12. >1.<50 aos >50.<200 ann >200 apa EM-202 0;. c. Rupture of steam gen-RM-G25 through X EP-390 ,I.O AP-530 ,R erator tube with loss of RM-G28, loss of AP-580 offsite power. feeder breakers, IM-202 Ih loss of lighting, AP-770 l27 etc. 9. SE00 TEARY SYSTEMi a. Rapid depressurization MS pressure, MSIV X X AP-460 of secondary system. actuation, feedwater MS line break out-EM-202 N; side containment flow, etc. t ENCIASURE_1 (Page 8 of 9) Page 39 EM-202 Rev. g 7
g} i i; o l LJ t'rmIFICATICII 0F EOSTUEATED ACCIDDrrS t.y t W M)ITION INDICATIONS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL DIERGENCY PROC. REF. b. Steam line break with RM-G25 through itM-G28 X X EP-390 'I primary-to-secondary leak. MS pressure, MSIV With >10 gpa With >5O gpa AP-460 actuation. primary-to-primary-to-secon-EM-305 p: secondary leak. dary leak with in-EM-202 H dication of fuel y damwe. c. Turbine failure. Turbine rotating com-X X AP-660 D'.. j ponent failure caus-Causing casing AP-580 -) ing rapid plant shut-penetration. Dt-202 fj f f! down. I '^ d. Ioss of Main and Emer-Feed flow, steam gen-X X X AP-380 gency Feedwater. erator level, RC HPI available. No core cooling No core cooling EP-260 3 available >20 min-available. Core EP-290 l( pressure, RC ten-utes. damage imminent. EM-202 perature, etc. [g .y
- 10. MISCELIJWE00S Q
h.{ AP-580 T ot, Reactor Trip. X a. RCS outlet temperature h EM-202 [.' >619'F. AP-580 b. RCS pressure >2500 psig RC pressure, Reactor X EM-202 or Code Safety lifts. Trip. ,I.[ AP-580 [.j 1 c. Incore Temperature Incore temperature X EM-202 j >700'F. printer. p. d. Other conditions that X X X EM-202 2-Increased aware-Activation of Activation of TSC,
- )
warrant: ness or require TSC, OSC, and OSC, EOF, monitor-plant shutdown EOF. ing teams and si per Technical public notification
- i/
1 i Specifications (e.g., excessive b, d cooldown rate, pipe crack, etc.) i l ENCIDSURE 1 (Page 9 of 9) EM-202 Rev. 2 7 Page 40 i ~ I l t~
m -...m_ .._-.,p.,,.....- ENCLOSURE 2 STATE OF FLORIDA NOTIFICATION MESSAGE FORM FOR NUCLEAR POWER PLANTS 1. A. TIME /DATE B. REPORTED BY (NAME/ TITLE) [ 2. SITE / A. Crystal River Unit 3 3. ACCIDENT CLASSIFICATION A. NOTIFICATION OF UNU5UAL EVENT C. SITE AREA EMERGENCY B. ALERT D. GENERAL EMERGENCY 4. EMERGENCY DECLARATION Time: Date: 5. INCIDENT DESCRIPTION OR UPDATE 6. INJURIES A. Contaminated / Number B. Non-Contaminated / Number 7. SITUATION INVOLVES: (NOTE: If A, go to item 13, otherwise continue with rest of form.) A. No Release C. A Release is Occurring-Expected Duration B. Potential (Possible) Release D. A Release Occurred, but Stopped-Duration 3. TYPE OF RELEASE IS: (Blanks are for specific nuclides, if available, i.e., I-131, Cs-137.) A. Radioactive Gases D. Radioactive Solids N/A B. Radioactive Airborne Particulates E. Non-Radioactive Gases C. Radioactive Liquids F. Other [] 5. RELEASE RATE: V NOBLE GASES IODINES Default (A) Curies per second (C) Curies per second Measured (B) Curies per second (D) Curies per second 10. ESTIMATE OF PROJECTED OFFSITE DOSE RATE: DISTANCE CHILD THYROID (mrem /hd WHOLE BODY (mrem /hr) l25 1 Mile (Site Boundary) 2 Miles 5 Mi'es 10 Mues 11. METEOROLOGICAL DATA (AT 33 FEET): A. Wind Direction (From) Degrees B. Sectors Affected C. Wind Speed MPH (MPH = 2.24 x meters /second) D. Stability Class 12. RECOMMENDED PROTECTIVE ACTIONS: A. No recommendations at this time. B. Notify the public to take the following protective actions: (NOTE: If message refers to 3600 radius, use the word "ALL" under sectors.) MILES NO ACTION SHELTER / SECTORS EVACUATE / SECTORS 0-2 n 2-5 i, ) 5 - 10 10 - 13. EVENT TERMINATED: A. NO: B. YES: Time Date 14. MESSAGE RECEIVED BY: Name Time Date EM-202 Rev. g _ Page 41
... 7 - - mi; W ; g.p~e , -r.s x, . n: im-
- o ;.t.-, :W sp %.'
s _ _. _..3, 3._ _ ENCLOSURE 3 26 (Page 1 of 2) U. NUCLEAR REGULATORY COMMISSION OPERATIONS CENTER EVENT NOTIFICATION WORKSNEET NOTIFICATION TIME FACILITY OR ORGANIZATION UNIT CALLER'S NAME TELEPHONE NO. (FOR CALL BACK) Crystal River 3 EVENT CLASSIFICATION Y N EVENT CATEGORY INIT. SIGNAL CAUSE OF FAILURE CENERAL EMERGENCY REACTOR TRIP / SCRAM MECHANICAL SITE AREA ENERGENCY ESF ACTUATIch ELECTRICAL ALERT ECCS ACTUATION PERSONNEL ERROR UNUSUAL EVENT SAFETY INJECTION FLOW PROCEDURE INADEQUACY 50.72 NON-ENERGENCY LCO ACTION STATENENT OTHER SECURITY / SAFEGUARDS OTHER TRANSPORTATION EVENT SYSTEM EVENT TIME ZONE EVENT MO. DAY DATE OTHER: COMPONENT: l l EVENT DESCRIPTION L' POWER PRIOR TO EVENT (Z): Did all systems function as required? YES If NO, Explain above. CURRENT POWER OR N00E Anything
- unusual
- or not understood?
NO If YES, Explain above. OUTSIDE AGENCY OR PERSONNEL CORRECTIVE ACTION (S) NOTIFIED 8Y LICENSEE STATE LOCAL RESIDENT YES NO WILL BE N00E OF OPERATION TILL CORRECTION: ESTIMATE TIME TO RESTART: j R j PRESS RELEASE ADDITIONAL INFORMATION ON NEXT PAGE EM-202 Rev.2,7 Page 42
QFggi6M.~ : LQ F x <. 3 2:.j.'. q J. ;, j l. _ 3 ENCLOSURE 3 26 (Page 2 of 2) ADDITIONAL INFORMATION FOR RA010 LOGICAL RELEASES LIQUID RELEASE PLANNED SOURCE (S): GASEOUS RELEASE UNPLANNED RELEASE RATE (C1/sec) : EST TOTAL ACTIVITY (Ci): RELEASE DURATION EST TOTAL IODINE (Ci): T.S. LIMITS GRAB SAMPLE MONITOR READING AREAS EVALUATED 7 Y N LIST BELOW PERSONNEL EXPOSED / CONTAMINATED Y N DESCRIBE BELOW PLANT NEALTH PHYSICS BACKUP REQUESTED 7 Y N NOTE: ONLY IF T.S. EXCEE0E0 OR ACTUAL CONTAMINATION A00!TIONAL INFORMATION r i s &%J A00!TIONAL INFORMATION FOR REACTOR COOLANT or STEAM GENERATOR TUBE LEAKS i SUDOEN OR LONG TERM OEVELOPMENT ? START DATE : START TIME : LEAK RATE : PRIMARY COOLANT ACTIVITY : MONITOR READINGS LEAK VOLUME : SECONOARY COOLANT ACTIVITY : CON 0ENSER T.S. LIMITS: HAIN STM LINE : SG BLOWOOWN LIST OF SAFETY RELATED EQUIPMENT ff.Q1 OPERATIONAL : SPECIAL ACTIONS TAKEN BY LICENSEE (if any) : / j iv) 1 EM-202 Rev.2 7 Page 43
p s.; % e.e P W l' N e ; _vi %. 1 _ ~"<W ENQ.0SJRE 4 mirr5114.S RR IE000ED PRmETIVE XTIG6 RR GASEDJS R.M EPOSLEE* MN ESENTIA. (DERATDE QPR1X PUCDGEL AD (MEJUE. PWU.ATI(N C00ITIO4 REE0tOCED ACTICN Tm mile rreautionary evacuation. Five mile,360*ler of ptentially effected sectors.**
- 1. A General Emergency has been &clared.
stel 2.AGggn$ "'"Nlhasbr4ss"d m s* ected. e" N p"Naff kNted sectors.** contai ilyre paj substant ssion grotct inventory in containnent.
- 3. A General Emergere has been eclared.
No conta fai h frQject Fission product inventory in containnent < GAS GP. 4 1 General Emenje been declamd. Five mile,360* tion of rotentially effected sectors." evacuation. astantial com in ptgmss or ected. Ten mile evacua nta1. ment failum miease likely not inminent. ission ;roduct inventory in containnent > GAS GW.
- 5. A General teen eclared.
Five mile, 360* tion of ptentially effected sectors." evacuation. ia core s or
- ected, mile evacua irment failure i to be rmnnent.
Iter areas wiicn can not be evacuated before plune No substantial fission ptcuct inventory in containnent. arrival.
- 6. A General Eme been eclartd.
Suostantial core in trogress. SM E AS M OVE Contairment failum is ected to be inminent. Fiss1on produ:t inventory n containnent > GAS GP.
- 7. M a:tual release has occurred or is in grogmss.
Ten mile. 360*, stelter, Tw mile rulati n is 'ected to be: 9 se to the shelter of ptentially effected sectors.** Wiole >0. to <. Ren Thyttid: >1.0 to _.0 Ren
- 8. M actual release has occurric or is in trogress.
Im mi' e, 360*, gvacuation. rulation is Irn)Ren se to the ected to be: Ten mi' e evacuation of rotentiall effected mctors.** a Wie
- >.0 to <5.0 Ten mi e shelter of renaining sec rs, b Thyroid:
.0 to T 25 Ren t
- 9. M actual release has occurmd or is in ress.
Five mile,360*, ion of rotentiall evacuation. se to tre b1 1 n is pajected to en mi e evacuat effected sectors." a hie . Ren en mi e stelter of renaining sec rs. b Thyroid: > 25 Ren DEEGCY KiKERS
- 1. M actual release has occurred or is in mss.
Control expsure of one w rkers exce for se to an energe wrte pajected be: lifesaving missiom to 'ahole y,1 Ren a W1 ole Body: to < en d. ate controls r ene try wrters b Thyttid: >l Ren ude ti tatiom and rts rators
- 2. M a:tual release has occurred or 's in ptgress.
C ntrol exp;u of one wrters rarfo 1na Dose to an ererge wrter 1s pqected to be: 1 savi uns nns to 7 Mule Bod Control of a) Wnle Body: 5 Ren time exp re wi' 1 be nest effective.
- Altre respirators stou' d be used W1ere ef ivetocontroIgh dose to enertlerry wrters, tilyroid tse nuy not be a limiting factor Tor 11tesaving missiors.
- t
- References for this table are a carbination of Tele 5.1, pge 5.31 Rev. 6/79 - Marual of Pmtective Actions for Nuclear Incidents and f0RECM)65%, dated 1A0.
sectors inclu&, as a mininun, the dwwind mctor(s) and atjacent sectors. EM-2T Rev. o 7 Page 44 ~
jiy. e.mW%y.r;WapjM^:?.;r"7trtT/595W#F.NOAM ^.;l,.
- N,;
y-j ENCLOSURE 4 (Page 2 of 2) GUIDELINES FOR RECOMMENDED PROTECTIVE ACTIONS FOR GASE0US PLUME EXPOSURE EVACUATION TIME ESTIMATE TABLES
- SECTORS Distance A-0 E-H J-M N-R All (miles)
Hr. -Mi n. H r. -Mi n. H r. -Mi n. H r. -Mi n. H r. -Mi n. GENERAL POPULATION (NORMAL CONDITIONS) 0 - 2** 1 - 30 0 - 45 0 - 45 0 - 45 2 - 30 0-5 1 - 30 1 - 30 0 - 45** O - 45** 4 - 00 0 - 10 3 - 00 3 - 00 0 - 45** O - 45** 6 - 30 GENERAL POPULATION (ADVERSE CONDITIONS) 0 - 2** 3 - 00 1 - 00 1 - 00 1 - 00 3 - 00 j?5 0-5 3 - 00 3 - 00 1 - 00** 1 - 00** 8 - 00 0 - 10 6 - 00 6 - 00 2 - 00** 2 - 00** 13 - 00 SPECIAL POPULATION (NORMAL CONDITIONS)*** 0 - 2** N/A N/A N/A N/A N/A 0-5 2 - 00 2 - 00 N/A N/A 5 - 00 0 - 10 3 - 00 3 - 00 N/A N/A 6 - 30 SPECIAL POPULATION (ADVERSE CONDITIONS)*** O - 2** N/A N/A N/A N/A N/A 0-5 4 - 00 4 - 00 N/A N/A N/; O - 10 6 - 00 6 - 00 N/A N/A 13 - 00
- These are conservative estimates and are inclusive of warning times.
l
- These estimates are for personnel on FPC property. Evacuation time is based on a staged / sequenced generating complex evacuation via the plart access road.
t
- This category includes the handicapped, elderly, and hospitalized individuals and is inclusive of the general population.
EM-202 Rev. g 7 Page 45
.-kkW,,y j::.;p%.3 7,.2:;p..co w w ng,xq,{ 42:yS;T a t. & w.w = W F m.L
- .:s
?N INFORETION SHEET FOR INERGENCY NOTIFICATION ENCLOSURE 5 7i ) 0F ON-SITE FPC nac1 min ?IONM v 1. Request to speak to the position designated for Emergency Notification. 2. Identify hourself (name, position, location)! 3. State: H IS H or H EQI A QRILL. CR-3 is in a*n) class. (Unusual Event, Alert, Site Area or General Emergency) 4. Briefly explain plant conditions causing this action (i.e., reactor trip, loss of instrumentation, actions taken to mitigate situation, dumped water into containment building). Basic Facts; Eq Coniecture S. State if release of radioactive material has been or is in progress, a. No radioactive material has been released from CR-3. DE b. Radioactive material has been or is being released from CR-3. 6. a. State. if evacuation or assembly should begin. O 1. No evacuation or assembly is necessary at this time, b QE 2. Begin standard evacuation or assembly and accountability proceedings at this time. Refer to Crystal River Coal plant Site Accountabil-l27 ity/ Evacuation Manual. l b. If CR-3 has evacuated, give a reason (i.e., evacuation of CR-3 non-essen-tial personnel has begun to limit confusion and improve communication on-site). 7. State if conditions are (best estimate):
- 1) improving, 2) stable, or
- 3) degrading.If ling permits and you itg1 cualified, ask for questions and 8.
state that further information will be issued as conditions warrant. O o EM-202 Rev. 2 7 page 46 - - ~
' f W.h, W. T u.k. g-4 e 'h op-gITE -.-.seva E'TIoss [2$ [ j Page 1 of 6 I The decistos to sheltar or evacuate shall be based on a concern for personnel safety and dose reduction. Shelterina may be the best alternative for does reduction in many cases. $heitering in interior roces will provide a whole-body dose rate reduction of approstaately 0.20. That 1.s. the dose rate (Rem /hr) for a person in an intertor roes of a unit will be only 107. of the dose rate predicted by the RAD 00gE model (or the dose rate measured outside the building). Dose rate reduction factors for thy roid dose through inhe14 tion of iodine are shown in the diagram below. The effectiveness of sheltering on reducing inhalation doses depende on wind speed (curves are shown for 1 aph, 6 oph, and 3 aph) and the length of time the building is in the plume. This is because outside air infiltrates into butidings faster when the wtad velocity is higher. Typical wind speeds at the Crystal River complex are between 6 and 8 aph. Thus, sheltering rapidly loses effectiveness for reducing tahalation thyrotd doses== typically, within two hours the inside dose rate to 15 percent of the outside thyroid dose rate. tenenessee e. asemettee rutere see to seentestee I t.. g ,s e I e.e l (1.4 wel l .a s I I me se e. i c..e, vii 0 I .s V enee, 6 e e e.no, vs l e t 4 e 4 W estestee (tesess ei tettetee Le e&ame sete s sede see toesesesseet,e og ut& seesseessee ee614tese esse steeee stesese eed eeeve. tvecuation reduces dose ae.cumulation by removing people from the plume area. If an evaeustion is ordered immediately after an emergency is declared in the plant, the time to clear the ette will be approminately 123 sinutes using the Flant Access Road. The corresponding time during adverse weather condi-tiene ta increased to 160 minutes. These times include 35 minutes for nottit* cation, assembly /aceounting, and equipment shutdown. If an evacuation is ordered at a time when these activittee have already taken place, the time to complete the evacuation can be reduced by 35 minutes. If a release of radioactivity to considered likely in the accident progression, consideration should be given to whether the evacuation will be ceapleted before the release starts. Once a rolesse starte, considetetton suet be given to exposure of evacuees during the avecuation. Refer to pages 2 and 3 of this enclosure for flow charts depicting en* site protective actione during $1TE AREA and Ct!stRAL ENERCENCY clasetfications. O EM-202 Rev. 2 7 Page 47 ~
q.g..ampy3.y; yde sy=:.mW v. wry. 'w;a:.~.- ~ -
- ~
'.u.'.Wi; E l. i. ' E .a4 l.a.g-g 3I, 3: 35 i 5 ~x t 3 c m c ('/ I 32 3 334
- .a
- .l HEs a
5:M.:i 2 E El I:
- s. s sn n,,
o.3 .sg gi o o~ .: a alil 2, at s w li oe de .i 8 ,,8 = = lll -a 1 1. S a ..i 2 5" es E 8 : e :E; jI 3:
- . s-
. s,ss e I! 33ij._gi i f, n 3.a_ i: na ^ sillili W II a
- 3 5
is msg =
- !=E.s:
3.: v ag 4 = O 3
- s as s.
a,a; 5: 8 se e x. n ,s, ; m_ ....c2. s c._. 2g.
- ag*:3 a
==:3:s.
a 4s ce s4 s_:.:
U.p
- g_d E.2 22 a"
- 3 5 "a-
-n
a:: ya g:
gl4:jtjg8: ..:.g 5 2 ! w, $ 4.5 ~* m g g 4 negg_a_,g s-s-a _ s s ! 8 a :. = i 3.E?g ?? I i I R E,E ".E !. c. W - ,,5-33$ = 7,) "a E2 a a sg.8 28. au 55E3:: Q= d -= j j_ g. S =
===; ((=4
- *"3 h
5 ea .i1.9 329i-
e::s sl.i al=sc2 se 11 silii 5:=
.n. a. s
- =
a s1 es sa g[jgl 2 5! 8 m/ 55 ! ? m sisie W ii ai s l=l=a=ss si . u, o s u s!i 151 s!. 2.2
- .e 9:lil a
J2*
- 1..:...
1:1 p) a 1 ( I.I it \\s 3 i ::s E R at .1 n -.~-
- ~
EM-202 Rev. 2 7 Page 48 .)
y q L ( b/ 4 i 1 a m l25 7 ON-SITE PROTRCTIVE ACTIONS Enclosure'6 FIAN CNART Fog cananmaL raaracasarf Page 3 of 4 4Y I I EVACUATE ALL MON-ESSENTIAL
- g
}V t PERSONNEL USING MOST EXPE-3 I j DITIOUS SEQUENCE FOR RE-D } NO LEASING UNITS. SEE EVACU-NO 3 l ATION PLANNING CUIDE TO j 3 PLAN THE EVACUATION.* 5 RELEASE I ) YES l I ANTICIPATED RELEASE i j ESTIMATED l I AT < 2.5 N HRS. I to YES ( M t 'Y j / WEIGH THE FACTORS BELOW FOR THE ACCIDENT IN 4 'r PROGRESS TO DETERMINE IF THE CREATEST DOSE
- 1 f*
SAVINGS WILL BE ACCOMPLISHED BY IMMEDIATE h l t EVACUATION OF DOWNWIND SECTORS: l N r I NO
- DOSE RATE / EXPOSURE DURATION l'!
M k
- ANTICIPATED DURATION OF RELEASE
- STABILITY OF METEOROLOGICAL CONDITIONS
^' ^ m YES RELEASE YES l CENERAL :) IN l> i j. PROGRESS IF IT IS DETERMINED THAT IMMEDIATE EVACUATION ye OF SOME AREAS IS NOT APPROPRIATE, TEMPORARY ( SHELTERING.IN ASSEMBLY AREAS.MAY BE USED UN-l{ 3 TIL EVACUATION IS DETERMINED TO BE PRUDENT. REFER TO PAGE 1 OF THIS ENCLOSURE FOR A DIS-p CUSSION OF ON-SITE SHELTERING VERSUS EVACUA-s TION. I L SEE EVACUATION PLANNING CUIDE TO Pl.AN i l-EVACUATION. M Ft R E i
.y:.:, as.%;an :k Cy, .n J.v. ': ~ - Th %:6-n'.' ~... z_ 05-SITE PROTECTIVE ACTIONS INCLOSURE 6 (25 h ITACUATION PLANNING CUIDE Page 4 of 4 } p sta stuNerteN astA / 9(sud Prep Detroes Blad Tomerd Seetero affeeted (A) W 349-11 8 EJE (3) WWE 12-33 ssW JtL (C) NE 3A-56 SW ELM (D) Ist 57-78 WSW LMN (E) E 79-101 W MNP (P) ISE 102 123 WNW NPQ (C) st 126-144 W PQR (R) $5t 147 164 NW QRA (J) 3 169 191 N RAB (t) SSW 192-213 NWE ABC (L) SW 216 236 NE 3CD (M) W5W 237 258 ENE CDE (N) W 259-281 E DEF (P) WW 282 303 ESE EFG (Q) W 304 326 st Pc5 (t) WW 327 344 Ss3 Ce} 3p8' }1* E ) / 8 -o-
== c p f, i O mu m CRYSTAL RIVER CENERATING COMPLEX l 203* 3 ,#' g. p \\ u 2,,. _L 8' y + 1 l',* *4 T Dette 6 6 $ Staff Adatststratten Parktag
- gyg, T
Co.etruction Wert rocce Perkins C Dette 1 & 2 Staff Adatatattattoe Parkteg ,QJo D Ustt 3 Staff Adelnistration Parktag 8 U;tte 16 2 Coat File Parktes 1 U;tt 3 Warehouses and Temporary Of fices 236* 12]o G K z,,. 1 ze\\. n " s Point e of coetect for personnel assembly are provided below SECTOR g ensrtArt A Unite 4 6 5 Catto 6 6 5 control soon &/C CE3 Adateistration $14g. Public Address System I/C North Coal Tard Unite 4 6 $ Centrel soom D/I C13 Warehouse Area Corporate Security Specialtet D/t put
- Ops frattere Corporate Security Specialtet E.P. C. and J Coal frate Area Unite 4 6 S Centrol pose
\\ J, E. and L South Coal Yard Ustte 1 6 2 Centret to e N Ustte 1 & 2 Dette 1 6 2 Centrol Been EM-202 Rev. g 7 Page 50 (LAST PAGE) ---.--~ - - -
Rev. 5 12/04/86 Document Section NFORM ATION ONL N C. R. Nuclear EMERGENCY PLAN IMPLEMENTING PROCEDURE EM'-201 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 l l 1 DUTIES OF AN INDIVIDUAL WHO DISCOVERS AN EMERGENCY O THIS PROCEDURE ADDRESSES NON-SAFETT RELATED COMPONENTS REVIEWED BY: Plant Review Committee f i /'/// I Date 12/04/86 Meeting No. 86-48 APPROVED BY: Dir., Nuclear Plant Operations 27 $S SM I A l2 0,l Vb Date O INTERPRETATION CONTACT: Nuclear Safety Supervisor _ _ x e cL; n --o. ~ ~ l'5 . "~'~iiTE' 11 +-
1.0 SCOPE 1.1 PURPOSE This procedure provides the action to be taken by an individual who discovers an emergency condition. I 1.2 DISCUSSION i Instrumentation cannot be the sole input tv warn personnel of an actual or potential problem. Properly trained plant personnel are essential so they can identify a problem and take appropriate action. Proper action by the individual discovering the emergency is imperative so the Emergency plan can be implemented as rapidly as possible. l l An Emergency Phone System is available for reporting emergen-l5 cies. This system enables an individual to report an emergency l by dialing 311 on PAX or conventional intra-plant phones on-l site, which activates a dedicated emergency telephone in the l Control Room. l O =0 5 Page 1 EM-201 Rev. t" u _._. ..e aw=.u m, :,m.,.-. a e c ~ w.:. m, c ~?~~~~'*' '~ ~~
=.. _..... 1.3 AUTHORITY Any individual dis:overing an emergency condition has the authority to implete.nt this procedure to the fullest extent of his qualifications. 1.4 DEFINITIONS 1.4.1 An emergency is an incident or condition requiring immediate attention, which could result in personnel injury and/or damage to plant components; it may or may not be accompanied by high radiation or radioactive contamination. Examples of an emer-gency condition include the following: a. Fire or Explosion b. Steam Line Break c. Accidental release of reactor coolant (RC), radioactive liquid waste, or other dispersal of radioactive material, d. High Radiation Field l 2.0 PRECAUTIONS 2.1 All personnel should be safety conscious and, therefore, alert to detect any unsafe condition which, if not corrected, could result in an emergency condition. 2.2 All personnel should maintain exposures ALARA (as low as reasonably achievable) and minimize radioactive contamination. EM-201 Rev. Page 2 l l 1 - K ~~" *: 5~~~~~- - A mv.m wm ~~
2.3 The 311 energency telephone number should be used for emergen-l5 cies QEI. l 3.0 RESPONSIBILITIES 3.1 All personnel permanently assigned to CR-3 shall thoroughly familiarize themselves with the following: a. The contents of this procedure. b. The locations of area radiation monitors and fire-fighhng equipment in, and the entrances to and exits from, the areas in which they work.
4.0 REFERENCES
4.1 Radiological Emergency Response P'.an 4.2 AI-1600, ALARA Program Manual 5.0 EOUIPMENT l l None 6.0 RECORDS AND NOTIFICATION None l l O ,0g EM-201 Rev. page 3
- 1..,
~.wn.,., n.u.pg.7.g;.7. sm.- .vm..,.x3 ;ge.... -
c,,..~,,.. ....m..- ~ m. ,,...~.. c.-#- w,,. w..: 3 ,z. u.2f. < _,,,u. 7.0 INSTRUCTIONS 7.1 An individual who discovers an emergency condition shall: 7.1.1 Notify the Control Room by dialling 311 on any PAX or conven-l5 tional intra-plant phones, giving the following information: l a. Name l b. Type of Emergency (fire, pipe rupture, etc.) l c. Location of Emergency d. Whether or not there are any injured personnel e.. Visible damage to plant components f. What action (if any) has already been taken l5 7.1.2 Take any immediate action he/she is qualified to perform that l will aid in controlling and minimizing the effects of the emer-gency, such as the following: a. Extinguishing a small fire with fire-fighting equipment located in the immediate area. b. Closing an upstream valve when a system pipe rupture has occurred. c. Locally stopping r.achinery tha't is contributing to the severity of the emergency (stopping a pump when the down-stream piping has ruptured, de-energizing a burning motor, etc.). d. Removing injured personnel from the affected area, if necessary, to minimize their exposure to further injury, high radiation, or radioactive contamination. e. Warning other personnel in the affected area to withdraw to a safe area, f. Any other information pertinent to the emergency. EM-201 Rev. page 4 1
,... ~.,,...: v,; ~ - ---v
- ~1,
- a.. a :.,
7.1.3 Withdraw to a safe area. 7.1.4 If possibility of personnel contamination exists, remain in the safe area until monitored. 7.1.5 Follow instructions issued by the Control Room. 8.0 ENCLOSURES None l l l i l l l l EM-201 Rev. D5 Page 5 (LAST PAGE) l . ? * " " ;".- - s - . :?* ---- .em ewamw ww... ev mm wn m mn u.sc. eere : n ww mm2>eA nmc _'j&, a. e
o A
- [ )
ESCAR REV 5 Date 12-12-86 AP-303 ESC ANNUNCIATOR RESPONSE ENTRY SYMPTOMS l CONDITIONS mz Symptoms, conditions and operator actions are contained in the attached matrix sheets. ] Document Section 1. NFORM ATION ONL Il C. R. Nuclear i g O THIS PROCEDURE ADDRESSES NON-SAFETY RELATED COMPONENTS l Reviewed By PRC [A I M & Date 12-11-86 Mtg.# 86-49 /d//0 h Date /2./7 r /4 Approved By NPM 7 .,.-..._-_._n.. =
CI'. TOR PAEL LOCATION ES-C-A AtNtNCI? AEL C VERTICAL C3tHN 1 o R8 StHP
- 1. rl R8 sung pung 3A or D auto start.
- 1. c) R8 supp ptarp start and stop.
HI-HI ANN PT PPS b) RB sunp punp 3A or 38 trip.
- 2. al Investigate possible leak sources.
3* AllK CDNT WO-21 TR0tBLE c) R8 suno level extra high. HI p' WD-131-LS WO-07 dl mste Disposal panel fan f ailure. LOW T.5* bD-222-L2 9
- 2. a1 0)angim EB sunp leve1.
5 C-t-1 ACI Di VALVE
- l. al ACI stesysten 1 or 2 bypass key in bypass.
- 1. al None.
SYST b) ACI stbsysten 1 or 2 nodule renoved.
- 2. al If suction is lost to Di sys due to closure TR0 TELE c) RC pass less than 200 psig and DIV 3 or of OtN 3 or 4, secure DH renoval and Div 4 closed.
correct reason for DtW 3 or DtN 4 closure.
- 2. al tbne.
i C-1-2 C-t-3 ES CABIET
- 1. al Failure of any cabinet fan.
- 1. al None.
FAN FAILtJRE
- 2. al ibne.
- 2. al Investigate fan failure and notify FSBFX ESA85 i
Electrical Supervisor. C-1-4 DH TO PR
- 1. al DiV 91 not full closed and RC press > 284
- 1. al None.
SPRAY ISD. psi.
- 2. al Close DtN 91.
284 psi RC-3A-PS7 DH-19 6 VV OPEN
- 2. al ibne.
Gl-16 C-I-5 RCTO DH
- 1. al Div 3 not full closed and RC pres > 330
- 1. al tbne.
SYST VALVE p si.
- 2. al Insure GIV 3 DIN 4, and DIN 41 closed.
330 psi 3 RC-3 A-PS8 DH-03 OPEN b) DlV 4 oct full closed and RC press > 330 284 psi 3 RC-38-PS9 D1-04 psi. RC3A-PS4 DH-05 c) Div 41 not full closed and RC press > 284 pst.
- 2. al ib closed indication on GIV 3, or DtN 4, or DfV 41.
C-1-6 BOR 6aT
- 1. al INST H1/Lov operate level at 47
- and 45*.
- 1. al Cut of f heaters.
47* f' STOR T#4K bl OWST low level alarm at 3* 9 3/8'.
- 2. al DWST Hi or Low level during operation 45' GI-It-LS Dit-18 LEVEL cl BWST Lo to level alarm at 2* 3 3/8".
secure operation causing uter transfer. 3
- 9-3/8" UH-007-LS DH-22
- 2. al Low level in BWST.
bl 8WST Lo level alarm following ES actuation 2* 3-3/ 8" i bl Hi@ 1evel in BW5T. shif t LPI & R8 spray suctions to R8 sunp. l C-t-7 BOR WAT
- 1. al BWST high tenp at 110*F.
- 1. al tone.
STOR TANK b) BWST low tanp at 60*F.
- 2. al If high alarm secure heaters, if laa place 60*F DH-9-TTS OH-18 T dip
- 2. al EMST tenp' indication high or low.
heaters in operation. Il0*F Di-10-TTS D1-22 bl Bor Wtr tenp cont non auto alarm. C-1-8 wit 00W TITLE 1. It0!CATED CDtoITI0t4 1. AUTO ACTION SETPOINT SO4 SING REFERENCE 2. (DNTROL ROOH It0ICATION WHIOl VERIFY OR 2. OPERATOR ACTID4 - VALID ALARM ELEtENT PIIPOINT TROUBLE nth 8ER & LOCATIQ4 I w-w .05
- e. 2 ae.
84CIATOR PAEL LOCATION ES -C-A AttuiCIA 'ML C VERTICAL CQ_LNH 1 e BCR E T
- 1. al BWET heater selector switch in local
- 1. c) tune.
TEMP C04T position.
- 2. al Place heater selector switch to auto 3A or SS/I DH-18 N04-AUTO
- 2. al ibne.
auto 38. DH-22 C-1-9 BOR E T
- 1. al Select switch is in auto 3A or auto 38
- 1. al Hone.
STOR TANK and BWST tanp < 65*F and heater selected
- 2. al If BWST level low restore level.
[11-to-TTS 21-18 HTR OFF breaker closing relay not energized. b) Inform Electrical Stpervisor of bmaker Dt-9-TTS DH-22
- 2. al Low BWST level.
failure. C-1 -10 RC-1 HI
- 1. al RC press 11500 psi and RCI HPI not FO
- 1. al One logic chame) trip in 2 out of 3 HPI logic.
BT-1 ESA-24 PRESS bypassed. B! STABLE
- 2. al Loss of RC/RC press.
- 2. al Investigate alarm and follow AP-380 TRIP (ESS A).
C-1-11 RC-2 HI
- 1. al RC press 1 1500 psi and RC 2 HPI not F0
- 1. al One logic chamel trip in 2 out of 3 HPI e
PRESS bypassed. logic. BT-2 ESA-24 BISTABLE
- 2. al Loss of RC/RC press.
- 2. al Investigate alann and fallow AP-380 TRIP (ESS A).
C-1-12 RC-3 HI
- 1. al RC press i 1500 psi and RC 3 HPI not FO
- 1. al One logic chamel trip in 2 out of 3 HPI PRESS bypassed.
logic. 1500 psi BT-3 ESA-24 BISTABLE
- 2. al Loss of RC/RC press.
- 2. al Investigate alarm an1 follow AP-380 TRIP (ESSA).
C-1-13 RC-4 LO
- 1. al RC press 1500 psi and RC 4 LPI not F0
- 1. al One logic channel trip in 2 out of 3 LPI L
PRESS bypassed. louic. 500 psi B T-7 ES B-39 BISTABLE
- 2. a) Loss of RC/RC press.
- 2. al Investigate alarm and follant AP-380 TRIP (ESSAl.
C-1-14 WIPOGJ TITLE 1. ItOICATED CotoITION 1. AUTO ACTION SEIPOINT SD4SitG REFERENCE 2. (DNIROL ROOH ItoICATION WHI04 VERIFY OR 2. OPERATOR Af T104 - VALID AL ARH ELEffNT PIPPOINT TROUBLE HlNBER & LOCATIO4
- ]
AP-303 Rei. P.yle 3 () h_
j l q "NCIATOR PAEL LOCATION ES-C-A M4ARI -AEL C VERTICAL COLitN 2 e NS CCC
- 1. c) Control switch in nonnal af t r st:rt
- 1. c) Alternata pmp stcrts es result of low BOOST Ptte position and breaker open, breaker racked fim.
CS/SC SW-05 TRIP in.
- 2. a) Insure alternate booster pmp starts.
CS/0 (SWP-2A) i
- 2. al Hismatch of target and indicating light on b) Investigate reason for punp trip.
SW-OS control switch. (SWP-28) 5 b) HSCCC booster ptmp auto start alann t (alternate pap). cl NSCCC booster pmp low flow alann. d) CR0H stator high tm p alarm. C-2-1 4 NS CCC BOOST
- 1. al Decreasing fim alternate pnp starts at
- 1. al Booster pmp starts.
SW-05 j PP AUTO-START 140 gun for > 2 sec.
- 2. al Investigate reason for pmp trip.
140 gpn SW-St-FS (SWP-2A) e 2._al Hismatch on control switch target and SW-06 indicating lights. (SbP-28) C-2-2 2 flS CCC BOOST
- 1. al Flm decreases to < 140 gpa for > 5 sec.
- 1. al Alternate booster pmp starts if < 140 spn PP LOW FLOW
- 2. al Both booster pmps running.
for > 2 sec. 140 gpn SW-91-FS SW-05 9 b) HS CCC boost psip trip alarm.
- 2. al Check CRDH cooling water filter for high SW-04 c) CR&l high tm p alarm.
A p and place standby filter in service. t C-2-3 a h I i 9 k f C-2-5 r BST-2
- 1. al Level at 35 f t. for high alana.
- 1. al None, g
LEVEL
- 2. al Investigate possible flow path to or frun 35 BS-5-LS B5-13 l5
[
- 2. al High tank levet indication.
tank and correct. 85-11 l i b) Restore tank to nornul level. E C-2-6 BST-2
- 1. al High tap alann at 110*F.
- l. al None.
TDiP b) Low tmp alann at 50*F.
- 2. al Check heat tracing for THIO tank for 110*F BS-8-TSI 85-13
- 2. al Abnonnal tank tenp indication.
proper operation. 50*F BS-11 C-2-7 C C C-2-8 WINDOW TITLE 1. INDICATED CONDITION 1. AUTO ACTION SETPOINT SENSING REFERENCE Il 2. CONTROL R00H INDICATION 6411 01 VERIFY OR 2. OPERATOR AClICH - VALID ALARM ELEMENT PD4 POINT TROUBLE NttlBER & LOCATION i
- i i
D5 '"9" 4 } AP-303 Rev. 7 i ~
34CIATGt PAEL LOCATION ES-C-A AMitNCI ^ 'AE L C VERTICAL CG_tHN 2 i h C-2-9 SOD If(D TM4K
- 1. a) tu@ level alarm at 34.5 ft.
- 1. al m ne.
4 BST-1 LEVEL b) Lo level alarm at 33.3 ft.
- 2. al Investigate possible flow path to or from 34.5 ft.
85-3-l.5 85-13 g
- 2. al Abnormal level indication.
tank and correct cordition. 33.3 ft. 85-11 s C-2-10 bl Restore tank to nornal level. SOD If(D TM4K
- 1. al lu@ teap alarm at 110*F.
- 1. al mne.
4 BST-1 TEff b) Low teap alarm at 50*F.
- 2. al Check heat tracing for sodium thiosulfate 110*F B5-7-151 85-1 3
- 2. al Abnormal tark tenp indication.
tank for proper operation. 50*F 85-11 C-2-11 y C-2-12 e RC-5-LO PRESS
- 1. al RC press 1 500 psi and RC 5 LPI not F0
- 1. al the logic criannel trip in 2 out of 3 LPI 3
BISTABLE bypassed. logic. 500 psi BT-8 ES&-39 TRIP
- 2. a) Loss of RC/RC press.
- 2. al Investigate alarm and follow AP-380 f
(ESSA). 5 L C-2-13 RC-6-LO PRESS
- 1. al RC press 1500 psi and RC 6 LPI not F0
- 1. al One logic channel trip in 2 out of 3 LPI BISTABLE bypassed.
logic. 500 psi BT-9 ESB-39 TRIP
- 2. al Loss of RC/RC press.
- 2. al Investigate alarm and follow AP-380 3
(E SS A). C-2-14
- )
r-L Wit 0Gd TITLE 1. It0ICATED (Dt0lTION 1. AUTO ACTION SETPOINT SD4SItG REFEREEE 2. (DNTIDL RCOM liOICATION WHIQ1 VERIFY OR 2. OPERATOR ACTIO4 - VALID ALARN ELEKNT f PItPOINT TROUBLE HLH8ER & f LOCATIQ4 i i .I 'i s, i AP-303 Res.
- Q I,-
Page S ~ v
A}44LNCT[ 34CIATOR PAEL LOCATION ES-C-A PAE L C VERTICAL CG.lHN 3 e
- 1. c) Breaker (nntrol switch in nornal after
- 1. a) RW 28 stcrts on decreasing header press u:
HS SEA WATER PP start position with bre.aker open. (Breaker at 25 psi. CS/SC W-02 NORH TRIP racked in.)
- 2. al Start RW 2A or 2B if auto start fails.
CS/0 RWOI j
- 2. a) Buss undervoltage.
b) Investigate cause of trip. C-3 -1 4 NS RW PP NORM
- 1. a) Overload relay is set at 115Z rated load.
- 1. al None.
HTR OVERLOAD
- 2. al High punp anps.
- 2. al Start RW 2A or 28 secure RWPl.
51 RWC2 W-01 C-3-2 NS RW SYST
- 4. a) Low press at 25 psig.
- 1. al RWP 28 auto start.
l LOW PRESS
- 2. a) Decreasing header press.
- 2. al Start standby HWP if auto start fails.
25 psi RS 63-PS W-04 b) Possibla W punp trip. b) Investigate cause of loss of press. W-03 1 C-3-3 NS SW PP NDR1
- 1. a) HWP 1 and RW 2A or GWP 28 zumang at the
- 1. al tone.
52 S/A W-02 i RtH WITH D1RG. sane time.
- 2. a) If both punps are not needed secure one.
(RW-1 W-Ol
- 2. al Indication of both punps rtnning.
2A,2BI C-3-4 ( C-3-5 NS CC
- 1. al Control switch in nornal after start,
- 1. al SW IB starts 2 sec af ter press decreases COOLING PP breaker open. breaker racked in.
to < 110 psi if SW 18 fails to start SWP NORM TRIP
- 2. a) Low system press alarm.
IA will start 5 sec. af ter press decreases CS/SC SW-02 b) SWP-18 or 1A start at 110 psi system header to < 110 psi. CS/0 SWO1 i pressure.
- 2. a) Insum auto start of SW IA or IB.
i c) Low bus voltage. b) Investigate cause of SWP IC trip notify Electrical Supervisor. NS CCC PP
- l. a) Overload relay alarm set at 1851 rated I. al ibne.
HORH HTR load.
- 2. al Start SW lA or IB secure SWP IC and 51 SWO2 OVERLOAD
- 2. al Low system pressure.
investigate cause of overload. SW-01 b) Hi!$ punp amps. i C-3-7 NS CCC
- 1. al High level alarm at 10.2 f t.
- 1. a) Hane.
TANK b) Low level alarm at 7.2 ft.
- 2. a) If low level alarm add nuke to surge tank 10.2 ft.
%I 37-LS SW-31 LEVD.
- 2. al Lcw or high N2 press, and investigate for leaks.
7.2 ft. b) Radiation alann in SW systen, b) If high level alann investigate for in t c) Low or high system pressure alann. leakage from let down coolers. C-3-8 1 Wit 00W TITLE 1. ItOICATED C0t0ITION 1. AUTO ACTION SETPOINT SDISItG REFERENCE 2. CONTROL ROOH DOICATION WHIOl VERIFY OR 2. OPERATOR ACTION - VALID AL ARM ELEffNT l PItPOINT TROUBLE HiHBER & LOCAfim AP-303 Rev. .0 5 M"6
^ 'meCIATOR PANEL LOCATION ES-C-A AM4JNC- ^ PANEL C VERTICAL COLLH4 3 I NS CC F
- 1. al High prcssurs alarm r.t 95 psig.
- 1. al HodIE j
TANK b) Low pr~ssurs alum at 75 psig.
- 2. al Check N2 regulitor f;r pioper operation.
95 psig h 134-PS SW-3' .I p PRESS
- 2. al High or la press indication.
b) If press alaam caused by high or low level 75 pssg ( b) High or 1 m level alarm. correct level. j c) Pmp anps not normal. 'i {. C-3-9 NS CCC
- 1. al SW purp suction tmp at 105*F.
- 1. al None.
l SYST HIGH
- 2. a) Loss of RWP.
- 2. al Check heat exchanger (or possible dirty 105*F W 5-TS
% 31 -i TEMP b) Screen wash trouble alarm. heat cxchanger and place alternate one in c) SWP abnormal current. service. i b) Check screens and RWP's to insure seawater flow to heat exchanger. i c) Reduce heat load on SW system if possible. NS CCC
- 1. al L a header press at 110 psig.
- 1. a) Start SWP 1A or 18.
j SYST LOW
- 2. al Tripped SWP alarm.
- 2. al Insure back up pmp starts.
110 psi % 151-PS SW-04 1 PRESS b) Possible SWP overload alarm. b) Check system for leakage. WO3 i c) Possible low surge tank press. ( C-3-il I I l NS CCC
- 1. a) One of 10 different inputs has caused alarm
- 1. al None.
W 46. -50, SW-18 SYST RB use annunciator typer to verify cause of
- 2. al Estaolish makeup to SW surge tank.
-54, -42, % 31 LEAK alarm. See note C-3-12. b) Isolate the affected conponent and place -4 3, -90,
- 2. a) High tmp alarm on affected conponent.
its backup in service. -107, -113, l b) Low coolant flow alarm if R8 air handling -95, and unit. -101-FS c) Level decreasing in SW surge tank. 4 C-3-12 8 w y'. RB AIR HAND
- 1. a) SW fim from air handling unit 3A, 38 or
- 1. a) None.
525 gpm SW-47-FS W 31 LOW EW FLOW 3C < 525 spm.
- 2. a) Check for leak and isolate leaking unit.
SW-51-FS W IS H
- 2. a) NS. CCC syst. RB leak alarm.
SW-55-FS f C-3-13 i i ISOLATION
- 1. al Supply air pressure decreasing to 80 psig
- 1. al Hone.
SWV-12, 35, l VLV on any of 22 SWV use annunciator typer to
- 2. al Restore air supply to affected valves.
80 psig 37, 41, 43, W OS ) AIR FAILURE verify cause of alarm. See note C-3-14. 45, 79, 80 TilRU %35
- 2. a) Instrurent air press. Im.
81 82, 84, ES,86, 109, 110, i ~. 353, 354, 3 355, 151, .. j and 152-PS C-3-14 i E I WINDOW TITLE 1. INDICATED CONDITION 1. AUTO ACTION SEiPOINT SENSING REFERENCE i 2. CONTROL ROOH INDICATION WHICH VERIFY OR 2. OPERATOR ACTION - VAllD ALARH ELEMENT PINPOINT TROUBLE NUMBER & LOCAT10N b AP.),3 llev. .05 ^* 7 I m
~ o '[d C-3-12
- 1. a) Diff flow to AH unit 3A 90 gym.
(2.34 psid) b) Diff flow to AH unit 3B 90 gpm. (2.34 psid) c) Diff flow to AH unit 3C 90 gpm. (2.34 psid) d) Diff flow to LD cooler 3A 50 gpm. (2.34 psid) e) Diff flow to LD Cooler 3B 50 gpm. (2.34 psid) f) Diff flow to CRDM'S 10 gym. (2.34 psid) g) Diff flow to RCP 3A1 20 gpm. (2.34 psid) h) Diff flow to RCp 3A2 20 gpm. (2.34 psid) l i) Diff flow to RCP 3B1 20 gpm. (2.34 psid) j) Diff flow to RCp 3B2 20 gpm. (2.34 psid) C-3-14 1. Supply air press decreasing at 80 psig of the l following valves: a) SWV-12 b) SWV-35 j c) SWV-37 (~' e) SWV-41 ~. f) SWV-43 g) SWV-45 h) SWV-79 i) SWV-80 j) SWV-81 k) SWV-82 l
- 1) SWV-83 l
m) SWV'-84 n) SWV-85 o) SWV-86 p) SWV-109 q) SWV-110 r) SWV-353 s) SWV-354 t) SWV-355 u) SWV-151 V V) SWV-152 AP-303 Rev. page 8 (LAST pAGE) ?,,, _. +.- . T'~~ ' ~~'
DOCUMENT TRANSMITTAL FORM 57360 FOR DOCUMENTS TRANSMITTED TO DC DESK.(NRC)* DATE: 29 DEC 1986 h [ BATCH: 465 DOCUMENT NUMBER SHEET NUMBER REVISION NUMBER COPY NUMBER AP 303 05 69 AP 303 05 70 EM 201 05 33 EM 201 05 ~34 EM 202 27(HKC12/29/86) 33 EM 202 27(HKC12/29/86) 34 EM 305 04 33 EM 305 04 34 EM 307 10 34 INSTRUCTIONS TO THE ADDRESSEE COMPLETE EACH OF THE INSTRUCTIONS BELOW WHICH ARE MARKED'WITH AN X j[_ (1) VERIFY THE DOCUMENTS RECEIVED AGREE WITH THE ABOVE DESCRIPTION js_ : ( 2) INCORPORATE THE TRANSMITTED DOCUMENTS INTO YOUR FILES ys_ (3) DESTROY DOCUMENTS OR PORTIONS OF DOCUMENTS SUPERCEDED BY THE ABOVE Jg (4) SIGN AND DATE IN THE SPACES BELOW INDICATING THAT YOU COMPLETED THESE INSTRUCTIONS. (5) SIGN BELOW INDICATING THAT YOU HAVE READ AND UNDERSTOOD THE CHANGES AS IDENTIFIED jg_(6) RETURN'TG DOCUMENT CONTROL, CRYSTAL RIVER UNIT 3, MAC# NA1C___NRZA)(_ FLA. POWFR CORP., P.O. BOX-219 CRYSTAL RIVER FLA. 32629 SIGNATURE OF ADDRESSEE DATE 0\\}}