ML20247Q667
| ML20247Q667 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/20/1998 |
| From: | Dube D NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20247Q664 | List: |
| References | |
| EPOP-4422A, NUDOCS 9805280311 | |
| Download: ML20247Q667 (37) | |
Text
. ,
I MILLSTONE NUCI. EAR POWER STATION EMERGENCY PIAN OPERATING PROCEDURE A 4 s.
n hr a
/[f,3 e
'0 [*9$ 1ii
,q, f?p}y.gygr ' ;ng g pr P' n;qx! HINKyypy3y ,cg3y' V yym F v y vg 1:EVIEW g as 1-w w +,
- ?,'%lq ,jk?% jf%al y"^Q \
Thermal Hydraulic Evaluation Methods EPOP 4422A ,
Rev.1 O
V
- ,s Approval: .
v w SORC Mtg. No: QSJ2D _
Date: 5 -/G -95r' Effective Date: 6 O/S-97 O Level of Use SME: D. Dube l General 9805280311 990520 PDR ADOCK 0500024S F PDR
)
Mllistone All Units
' Emergency Plan Operating Procedure v
Thermal Hydraulic Evaluation Methods TABLE OF CONTENTS
- 1. PURPOSE....................................................2
- 2. PR E R EQ U I S ITES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
- 3. P R ECAUTI O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '. 3
- 4. I N STR U CTI O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 4.1 Evaluation Selection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 4.2 Time Until Core Uncovery . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4.3 Rate and Extent of Core Damage . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 4.4 Protective Boundaries Status . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 4.5 Time Until Containment Failure . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 4.6 Core Cooling Water Reserves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 4.7 Continuation of Millstone Unit 1 - PCF . . . . . . . . . . . . . . . . . . . . 10 1 4.8 Subsequent Actions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11
- 5. R EV I EW AN D S I G N O FF . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
- 6. R E FE R EN C ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
- 7. S U M M ARY O F CH AN G ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 ATTACHMENTS AND FORMS A,ttachment 1 " Time Until core Uncovery Estimation" . . . . . ........ 14 Attachment 2 "Worksheet for Estimation of Fuel Damage States" . . . . . 18 Attachment 3 " Protective Boundaries Status Determination" . . . . . . . . . 32 Attachment 4 " Time Until Containment Failure Estimation" . . . . . . 34 Attachment 5 " Core Cooling Water Reserves Status Determination" . . . 35 s
v Level of Use EPOP 4422A STOP THINK ACT REVIEW Rev.1 General l 1of36 k
. 1. PURPOSE
?
(V 1.1 Objective Provide guidance to the Technical Support Center staff in performing initial thermal hydraulic evaluations that may be performed during an event that activates the Station Emergency Response Organization. These evaluations include estimation of the following:
- Time remaining until core uncovery
- Fuel damage states Protective boundary status Time remaining until containment failure
- Cooling water reserve status Continuation of Millstone Unit 1 primary CTMT flooding 1.2 Discussion p The MTSC has the responsibility for the performance of the calculations (j in this procedure. The MTSC may delegate this task to any qualified TSC staff member.
Once the TSC is fully staffed the Accident Management Team will relieve the MTSC of this responsibility and may employ more sophisticated models or methods in making engineering evaluations.
l.3 Applicability N/A f
I o
V EPOP 4422A Level of Use-STOP THINK ACT REVlEW Rev.1 General 2 0f 36
- 2. PREREQUISITES 2.1 General N/A 2.2 Documents 2.2.1 EPUG-ll," Guidance for Millstone Unit 1 - Primary Containment Flooding" 2.3 Definitions 2.3.1 EPUG - Emergency Plan User's Guide 2.3.2 ME - Mechanical Engineer 2.3.3 MTSC - Manager of Technical Support Center 2.3.4 PCF - Primary Containment Flooding 2.3.5 RVLMS - Reactor Vessel Level Monitoring System 2.3.6 RPV - Reactor Pressure Vessel
- 3. PRECAUTIONS N/A O Level of Use EPOP 4422A ST P THINK ACT REVIEW Rev.1 Genemi 3 0f 36
,_ 4. INSTRUCTIONS A <
g.
V 4.1 Evaluation Selection 4.1.1 SELECT an evaluation from the following list:
Time remaining until core uncovery, Go To Section 4.2 1 '\
l .
Rate and extent of core damage, Go To Section 4.3 Status of the protective boundaries, Go To Section 4.4
. Time remaining until containment failure, Go To Section 4.5 1
. Cooling water reserve status, Go To Section 4.6
' I Continuation of Millstone Unit 1 - Primary Containment Flooding, Go To Section 4.7
- End of Section 4.1 -
J n
b Level of Use EPOP 4422A STOP TillNK ACT REVIEW Rev.1 General 4 of 36
. 4.2 Time Until Core Uncovery b' 1, C A UTIO N If RCPs are operatin,g or if reactor vessel is above 29% (MP2), or 64% (MP3) this section should not be used.
4.2.1 Refer To Attachment 1 and PERFORM the following:
- a. ENTER required data. ,
- b. CALCULATE time until core uncovery.
1
! c. REPORT time until core uncovery to MTSC.
l
- d. NOTIFY MTSC that the value was determined using Attachment 1.
l l
4.2.2 CONSIDER use of other methods available to the Accident Management Team to determine time until core uncovery, as necessary.
3 (V 4.2.3 Go To Section 4.8.
- End of Section 4.2 -
EPOP 4422A Level of Use ST P THINK ACT REVIEW Rev.1 General 5 of 36
43 R 'I'o e imen 2 nd PERFORM the following:
- a. ENTER required data.
- b. CALCULATE rate and extent of core damage.
- c. REPORT rate and extent of core damage to MTSC.
- d. NOTIFY MTSC that the value was determined using Attachment 2.
4.3.2 CONSIDER use of other methods to determine rate and extent of core damage, as necessary.
4.3.3 Go To Section 4.8.
- End of Section 4.3 -
Level of Use EPOP 4422A ST P THINK ACT REVIEW Rev.1 General 60f36
. 4.4 Protective Boundaries Status 4.4.1 Refer To Attachment 3 and PERFORM the following:
- a. ENTER requ.ted data.
- b. DETERMINE status of protective boundaries.
- c. REPORT status of protective boundaries to MTSC.
- d. NOTIFY MTSC that value was determined using Attachment 3. .
4.4.2 CONSIDER use of other methods to determine status of protective boundaries, as necessary.
4.4.3 Go To Section 4.8.
- End of Section 4.4 -
C i
i lO Level of Use EPOP 4422A STOP THiNK AOT REVIEW Rev.1 General 7 of 36
l
. 4.5 Time Until Containment Failure 4.5.1 Refer To Attachment 4 and PERFORM the following:
- a. ENTER required data.
- b. CALCULATE time until containment failure.
- c. REPORT time until containment failure to MTSC.
- d. NOTIFY MTSC that the value was determined using Attachment 4. .
4.5.2 CONSIDER use of other methods to determine time until containment failure, as necessary.
4.5.3 Go To Section 4.8.
- End of Section 4.5 -
n -
V I'
l 1
I C Level of Use EPOP 4422A l' STOP THINK ACT REVIEW Rev.1 General 80f36 ,
, 4.6 Core Cooling Water Reserves n
.C 4.6.1 Refer To Attachment 5 and PERFORM the following:
- a. ENTER required data.
- b. CALCULATE time to deplete cooling water reserves.
- c. REPORT time to deplete cooling water reserves to MTSC.
- d. NOTIFY MTSC value was determined using Attachment 5.
4.6.2 CONSIDER use of other methods to determine water reserves status, as necessaav.
4.6.3 Go To Section 4.8.
- End of Section 4.6 -
C
~
t-l-
C >
Level of Use EPOP 4422A STOP THINK ACT REVIEW Rev.i General 90f36 N
. 4.7 Continuation of Millstone Unit 1 - PCF 4.7.1 Refer To EPUG-11," Guidance for Millstone Unit 1 - Primary Containment Flooding," and PERFORM the following:
l a. EVALUATE continuation of Millstone Unit 1 - PCE
- b. RECOMMEND whether to continue Millstone Unit 1 -
PCF to MTSC.
4.7.2 IE conditions change that may affect continuation of Millstone Unit 1 - PCF, REPEAT Section 4.7.
4.7.3 Go To Section 4.8.
- End of Section 4.7 -
0 U
t n
' U Level of Use EPOP 4422A ST P THINK ACT REVIEW Rev.1 General 10 of 36
4.8 Subsequent Actions
,es bl 4.8.1 ANALYZE ongoing conditions.
4.8.2 REPEAT thermal hydraulic evaluations, as necessary.
4.8.3 RETAIN all calculations.
- End of Section 4.8 -
l
[
V I
)
1
, m, 1 ks Level of Use EPOP 4422A STOP THINK ACT REVIEW Rev.I General ll of 36 I
I j
1 l
l l .
- 5. REVIEW AND SIGNOFF l C 5.1 N/A
- 6. REFERENCES 6.1 " Thermal Hydraulic Reference Book" I
- 7.
SUMMARY
OF CHANGES 7.1 Changed procedure from an NU common procedure (NUC EPOP) to a Millstone Nuclear Power Station Emergency Plan Operating Procedure (EPOP).
7.2 Deleted references to CY in all applicable locations.
7.3 Deleted DSEO, MP1, SERO, SORC. and TSC from the definitions section.
7.4 Deleted all attachments applicable to CY.
7.5 Changed Wide Range Level to RPV Level (Fuel Zone)in Attachment 1, step 1, Millstone Unit 1.
/m
(" ) 7.6 Added parenthesis and ft /3 min to final step of equation in Attachment 1, step 2, Millstone Unit 1.
7.7 Added note to Attachment 1, step 2, Millstone Unit 1, to clarify that the calculation rate of liquid loss should be a negative number.
7.8 Deleted a negative sign from the numerator and added an absolute value sign in the denominator to the equation in Attachment 1, step 3, Millstone Unit 1.
7.9 Changed Attachment 1, step 1, Millstone Unit 2, to record the reactor vessel level and time just prior to a change in level.
7.10 Added note to Attachment 1, step 1, Millstone Unit 2, to clarify that the RVLMS Level indicates that the liquid volume is greater than or equal to the value in the table.
7.11 Added parenthesis and units of ft 3/ min to final step of equation in Attachment 1, step 2, Millstone Unit 2.
3 7.12 Changed Attachment 1, step 1, Millstone Unit 3, to record the reactor vessel level and time just prior to a change in level.
(
V Level of Use EPOP 4422A ST P THINK ACT REVIEW Rev.I Gemal 12 of 36 l
7.13 Added parenthesis and units of ft 3/ min to final step of equation in g Attachmeni 1, step 2, Millstone Unit 3.
7.14 Added parenthesis and units of psi / min to final step of equation in Attachment 4, step 1.
7.15 Added parenthesis and units of min to final step of equation in Attachment 4, step 2.
O O Level of Use EPOP 4422A ST P THINK AT REVIEW Rev.I Genera 13 of 36 ,
._J
'. Attachment 1 Time Until Core Uncovcry Estimation
, (Sheet 1 of 4) m l ]
Millstone 1 1
1
- 1. RECORD the reactor vessel level (0FIS Display A3) change data:
Clock Timei(T i ) Leveli inches Clock Time 2(T2) Level 2 inches (T2 > T i )
OBTAIN level data from the RPV Level (fuel zone) instrument for times near the current time in the event.
OBTAIN the liquid volumes from the following curve:
Liquid Volume vs. Lewl 10000 p _._
9000- - . .
~ " ~ ~
,_ -127 in., 5685 cu. ft.
V j 6000
> 5000 3 4000 - - --- ---.
.!r __
3000_. _.
g -
2000 - -- _ ___
a: _ _ _ _ .
1000 -
- 0 ---
-500 -400 -300 200 -100 0 100 Fuel Zone Level (inches) l Top of Active Fuelis at -127 inches,5885 ft 3 I i
- 2. CALCUIATE rate of liquid loss (time in minutes) d_y _ U2 - V i ( )-( ) ( ) ft3 {
dt T-T 2 i ( )-( ) ( ) min Note: This should be negative number r
b Level of Use EPOP 4422A STOP THINK ACT REVIEW Rev.I General 14 of 36
Attcchment 1 Time Until Core Uncovery Estimation
. (Sheet 2 0f 4)
Ci '
Millstone 1 l
- 3. ESTIMATE time to reach Level of Core Uncovery CU)/ Fuel Damage Remaining Time to Core Uncovery = At uncovery -
2 - Vcu) 2 dt i
3 where Vcu = 5885 ft RemainingTime = ( ) - 5885 ft3 = minutes
( )
Clock Time to Core Uncovery = Tuncovery = T2+ Atuncovery =
? !
I i
l l
"O~ Level of Use ' EPOP 4422A ST P THINK ACT ' REVIEW Rev.1 General --
15 of 36 i 4
Att:chment 1 Time Until Core Uncovery Estimation
, (Sheet 3 of 4) g.
L Millstone 2 C AUTION l This calculation should not be used while RCPs are operating or when level is above 29%.
l 1. RECORD the reactor vessel level (OFIS Display A3) and time just prior to, a change in level:
l Clock Timei (Ti ) Leveli %
Clock Time 2(T2) Level 2 %
(T2 > T i )
OBT'JN the liquid volumes from the following table:
RVLMS Level (%) Liquid Volume Note: The RVLMS Level (ft3) indicates the liquid volume is y -
greater than or equal to the value in the table.
12 397 19 497 29 1415
- 2. CALCULATE rate of liquid loss (time in minutes) dV
=
V-Vt 2
=
( )-( ) =
(
3
) (ft )
dt T-T1 2 ( )-( ) ( ) (min)
- 3. ESTIMATE time to reach Level of Core Uncovery Remaining Time until Core Uncovery = Atuncovery = - (V2) = minutes
(.dY) dt Clock Time to Core Uncovery = Tuncosery = T2 + atuncovery =
l-L See Attachment 5 for Core Cooling Water Reserws Determination.
EPOP 4422A Level of Use gOneral STOP THINK ACT REVIEW Rev.1 16 of 36
~
Attachment 1 Time Until Core Uncovcry Estimation
, (Sheet 4 of 4) i m
l b,) Millstone 3 I
C A UTIO N This calculation shoulci not be used while RCPs are operating or when level is above 64%.
- 1. RECORD the reactor vessel level (OFIS Display A3) and time just prior tq a change in levels:
Clock Timei (T i ) Leveli %
Clock Time 2 (T2) Level 2 %
(T2 > T i)
OBTAIN the liquid volumes from the following table:
RVLMS Level (%) Liquid Volume (ft3) p 19 308 -
V 32 433 47 558 64 1591
- 2. CALCULATE rate of liquid loss (time in minutes) dV
=
V-VI 2
=-
( )-( ) =
( ) (ft3) di T-Ti 2 ( )-( ) ( ) (min) {
1
- 3. ESTIMATE time to reach Level of Core Uncovery !
(V2)
Remaining Time until Core Uncovery = Atuncovery = - minutes (g) dt
=
Clock Time to Core Uncovery = Tuncovery = T 2+ Atuncovery =
See Attachment 5 for Core Cooling Water Reserves Determination.
?
(U Level of Use EPOP 4422A ST P THINK ACT REVIEW Rev.I General 17 of 36
~
Attachment 2 Workshcet for Estimation of Fuel Damage States (Sheet 1 of 14)
(~h V 1. ESTIMATE or IDENTIFY clock time to core uncovery, Tuncovery (Attachment 1).
- 2. CALCULATE clock time to start of fuel heatup as follows:
Vnoilxbr,
+ Iuncovery b
ursatPox 1 x Po(Mw) x 948.0 M / ( sec. " w. ) x 60.0( m* in./#' \
Where.
Vboil = Top half of core volume (ft 3, Table #1) ..
P/Po = Decay heat fraction (Refer to decay heat fraction vs. time after trip plot)
Po = Initial core power (Mwth, Table #1) hrg = Heat of vaporization (Btu /lbm, Table #2) vrsat = Saturated liquid specific volume (ft3/lbm, Table #2)
- 3. READ time to various fuel damage (core condition) states from the attached unit specific fuel temperature vs. time after start of fuel heatup figures and Table #3. l (Note: Times are referenced from the start of fuel heatup as calculated from step 2 above)
Table 1 Plant MP1 MP2 MP3 Vdoii(ft3) 1057.0 627.0 662.0 Full Power (Mwth) 2011 2700 3411 Table 2 Pressure (psia) 50.0 1000.0 2000.0 vrsat 0.017274 0.02159 0.02565 hrg 923.9 650.4 466.2 Table 3 Core Condition Fuel Cladding Temperature (F)
Gap Release (cladding failure) 1500 Fuel Overheat (grain boundary) 2500 Core Meltdown >3500 Analysis Assumptions: No ECCS injection and 1007c initial equilibrium core power EPOP 4422A I Level of Use ST P THINK ACT REVIEW Rev.1 Genew 18 of 36
I
-pQ A 2
2 4
0 4 6 _
0 0
PI 3
~ -
0 1
O v. fo
. . ~
. . _ _. - .. P e 9
_ . - ~ - _.. _. _ ~ .Z - .
.%__ ER1 _
.[ _ - - . _. .
_ ~~ - ._
_ _ ~
_._- _ ~ -- __ _-
- - __ s___
~
_. _ ~
- .~
.. _.~ .
h_.__
- ._'~
. ~ -
_ _I
~
2 l- ___ _._
_...m
~
_.__- _ _ ._-~
0 s . .
0 t
e 0 1
t a
)
S ~
e e up '
g a i u mm _ -
W T B . ' - ~ . E N
m s. ge
_ L - .
_ l
__._ I V
E a v ar - _ -
R D n ev
~ .
- _. N .. )
n l
e i oA . ~ _
[
i m
2 u t s -
_I .. (
F) 4 c a h __ _.
T
. ~
___ ._ p C t
2~. _
t nf r no _
~
i r A e of 1
F M 0 T 0
p)L m n 2o t a 6 e 3 1
t r
e -
h ot H se
- f A
ci te e . .. .
e K a ah y m _ . -
m N t
a u Ai mS y t (
c ss __ .__.
i T
I H
e A T t .
s D (
_ . - ._ - ~ .~
.___ _.. .s.~~
E
_~__.____
r -_ _. -
f o
P .
t _
~
~ ._._
O e _. _. - _. -
._ T S
. - _ ~
e .
~
h --
s
_ - _. _ 0 k _
. _ y+
1 r _
~ _
__.N __
1
_ o _-._ _ .
. _s _ _
W . g_.
__ ^
I
~ y __
~
h_ -
~
iI
%~ K~ -
u_
. _. ~ _
_ ~ _
. ~ _
~
~
~
1
_ 0 5 0 5 5 0 5 0 4 3 0 0 3
0 2
0 1
0 1
0 0
0 0
0 e 0 0 0 0 0 0 0 0 sl Ua r -
5 o nee m f mb le vG e
L
{
lll ll l
DN P I
A 2
2 4
4 0 6
- 0 8
P1 3 1 O P e
- v. of R20 0
0 6
1
/ .
0 0
4 t
t s
e a
3
/ 1 S
e 2
0 u
)
p d "
p 0 g
a 0 mu i h
0 2 ) W
= D T _
1 c
E m n e e g
e I V
a o g (
s E s
a r R
D i ,
t r e p l
c ev A v u e ra A 0 o t 2 u F sh 0 0 oh
- T t F ) t t n -
1 l C 4 a e nf e o 1
e o
/. " .
u A Omn h o f
3 0 HM y
a 3, 6
f f
o s,
t t e : r ci t e c s 0 a t
a a h S
e w / _
0 8
t s K N
t m ( D o dr r
e I Ai ,Pl f t H T
i t 1 .
lu h a s P T .
E f
r o
M F
( t H
o l , 0 T 0
i e
m P
[# /
6 t
O e T e S h 8 s
a// -
1 t
k
- r o n 0 0
// /
i o 4 F t 0
a oW F 0
0
)
N 2
t a
id C
d x
A, g
0 n 5
t i
n a 0 -
a 0 -
l i
y 2 t -
n .
b ae 2
E mi l d
e r
W Z i la C O
0 0 0 0 0 0 0
y e 0 0 0 0 0 0 5 0 5 5 4 3 2 1 sl _
Ua r. -
b > }*
o ne .
f O le vG e -
e L _
1'
M 0
0 5
2 d
ir w
id o
c r .
0 0
0 2
s t
e /
a S
t e
g 7
1 0.p 0
)
u
/ .
a m .-
= u m n B a o eo d p 0 0
D i t
c s
r i
h 5 p l
e a r v A e T g
o -
- 1 2 u F t F n f
)
4 1
t s
o ht s
n a
t s
v e o f H M o A '
mn o '
4 y 6 l
h oi t
e a 3, c t e c r /
t a a h S
e e D wo
.A t
i m (
,P s 0 e 0
t 1 s
J 0 a P
l
_ E lu dr
/ 1 M F f i
_ ( t r
f o
T M j H
t e N-
/
e g h
I
_ s
_ k W '
r W
o F 0
H W
n o ,j ' 0 0
5 F
0 0
2 W f/ s 0 t d
0 a m
8,Y/
5 s t
a e p lt t u
_ lts i
r d mHe e t
. M E i 2
O t a U
ir Z C l
M 0 m0 0 0 0 0 0 0 0 , 0 0 0
0 0 0 0 0
0 0 0 o 0 5 4 5
3 3 5
2 0
2 5
, c, 5 e~ hE I
M 0
0 0
3 M _ -
T d _.
Q i/ 0 0
J 5 2
s j t
e _
t a _
3 S 1 )
p _
e 0 u _ 0 0
g a
0
= B m
u -
0 2
m n e d a o g a
ir h
D i t
c e r T l
a v e e r A g a --
2 uF F s r
) ht -
t t n v n f 4 1
s o o A 0 e o - 0 H M f
o 5 mn 5 y 6 3
i 1
h o t a .
c t ee i
c r e
a a h S
e w t
t m ( D o /
A i , P .l '
t 1 l
- I lu E
s P F H /
M
( 1 T
r 0 o t
- o 0
/
f H 0 t
e
/ 1 e 7 -
h s 1 s
a / ,
t k -
r -
n o o W
F 0
0 F
0 0
2 n d li d
i c
s r /
d ,
/ 0 0
5 0
5 s a t
a s
lt e
l s
ir a
bu ae i
p t
iy/
M E: dH $
r
- 2 O
- e e j U rc _
0 0 0 0 0 0 0 0 0 0 0 0
0 5
0 5
4 0
0 4
0 5
3 0
0 3
0 5
2 0
0 2
0 s
i a, 0 5
ep hm.
f
C 0
0
- - - 4
- dr i
t
- T - -
/ .
0 0
- ld o - - / _- .
5 3
- C - -
p -
/,
s - - - . 0 0
e
. 0 t . 3 t
a -
8 - - .
) -
S 0 p e 0 u - d -
g n r
i i
0 u h - -
/
a = B
'e - - -
- 0 n 0e m p a
0 5
a o ar - - -
D i t
c e v A r
e v
p _
2 a A l -
e r s 2 u F h -
F ) - - .
t -
t t a no n fo 4f 1
e M
- 0 e H 6 0
o 0
m n 6 o y 3
/ .
2 h t a e r c t e i _
a a he c w -
e o
/
S D P t
t m ( g - / _ p _
s A
i l P lu 1 T p -
t -
- 0 s F t 0
E M
(
R - -
- / ? T 5
_ 1 r
f o
- p y # .
t - -
- - - F s e -
0
/,',
e -
- 0 h - - - -
1 1 0 s - _ 0
._ k a 0
- - / _
_. Wo r
F it n
o s
,/ ~
1
.. F
- - m d i
i
- -f -
2
_ 0 - 2 O _ f 0
0 5
l a_
t p
d n
a s 0 0
t a - N p 5 t t i t
- M a m
2 EmHe d g.
- 0 -
ltda i
_ _ 0 - Z C s 0 0
0 0 0 0 0 0 0 0 g o o 0 0 0 0 0 0 g g o
. 0 5 0 5 0 5 0 5 g $
- 5 4 4 3 3 2 2 1 1 C* > jE
M 0
0 0
0 1
i i
h l
m
/ > 0 0
% / 0 9
j 0 0
0 8
s S
t t
e a 3 1
)
p u
d s
i T
'p 0
' 0 2 m p 0 e
g 0 u 4 r
7 0 B e -
a e 1 m = g A -
a a n r e - 0 D o v 0 i
t A }
/ 0 l c s 6 e a ht Y 2 u F r n ,
t F ) o / -
n fo 4 1
t s 6 M }
~
0 e f o d / " -
0
- m n o H 3r .
i h A / - 0 7 t 5 h ioe y e c
t e a ow t
o / -
t a a h c F t S e P /
t A i t
m (
D lu ,
F l
j f , 0 0
/'/
s 2 t
- 0 E P o 4 r M H ( -
o f
t F
/s ' ' - 0 0
e C 0 e '/
h k
s r
0 11 a
i G
/ 3 W
o F ie o
5 , 0 0
g '
s d 0
- F m i. 2 9
O g 0
0 5
0 2
m . M a
)
/ 0 wk t
a p 0 w s e
0 1
UmH M $
e a d g M C 1
7 # 0 0
0 0 0 0 0 0 0 0 0 0
0 5
0 5
4 0
0 4
0 0
3 0
5 2
g 0 5
1 0
0 1
0 5
C- E
M
_ 0 0
_ 4 1
_ dr
_ h T
f l
o C
_ )/ f 0 0
) r 2
1
/ .
s e
/
t 0
/
)
_ a p 0 0
t 7
S 1 m d 1
e 0 i g h p 0 T
= ge
_ a e
_ m a
n a g a
o m e
D i t A c A v
0 l
e a r
0 8
F 2 u s,
h I
F t
n f e o
)
4 1
t s
o 6
'] / .
f H 3, mn h oi c e 8
t o
y a
c 1
i r
JI
/
)
/
/
t a a hS e
e h
T / _ s 0 D , 0 t t J
m o t
A i
(
, H
/ [ 6
_ t 2 s P E M
_ r
//
/
. f o
t e
e F$
0 0 0
s/
(
_ h 8 4 1
s k a f
r m o
F t e W
F 0 d 1
u 6
0 0
0 2
2 O t
a I
u r
/#s 0 0
2 5 s e
a t
a p t
s ft t u
r lt e b e n
_ e M E r
H
_ - d 2 i e
- 0 0
ir i Z C /
_ 0
_ 0 0 0 0
_ 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
5 5
4 0
4 5
3 0
3 s
e 0
2 m
t 0
0 1
5 C~ n ]"-
n)_ M 1_ 0
, 0 6
1 I
d ;
T d / 0 0
4 1
y s # 0 0
t e dr p 2 1
)
a 3 p
u h S
t 1
0 m T
u e
g 0 B e
e e
a = g v a A - 0 n
m r 0 0
a i o ev 1 D t c As J l
e a r ht s 2 uF t )
4 F
t a m n
o
'/
/ -
n f e o 1
e 6 dr / / - 0 H 3r f > 0 o h
_m n h oi 9
t y e a w T
o
/ 8 c t e
a a hS e c o e P H / -
t t
A m ( D Nu F
/-
i t 2 -
s P o t - -
0 0
E M H 6
_- r
(
o -
_ f h
t e
e s
F'
)
X 9
1
//s '- " 0 a
' 0
. k -
, 4 r - n
_- o -
F W - W k
s p
- M @ M, g -
t a
s d
n a
/ ' 0 0
g - e 2 d y i t
{'
__ g - -
b r
u -e a
dg
- E l
._ g r
d h
g s
i
_ - Z C l
0 0 0 0 0 0 0 0 0 0 0 0
0 5
0 5
4 0
0 4
0 5
3 0
0 3 - 0 0
2 0
5 1
0 0
1 0
5 C~
O,_
M 0
1 0
5 2
m e
- }b
/
/ . 0 0
,' 0 2
s e
t a )
p
/
S t
0 u p e
0 0 mu Ne g 0 B a e g
=
g a m
a n
o m a w 0 A 0 D i t
c A 5
l e a r hs ;f
' 1
)
t 2 u F no
.n f t F 4
)
1 t
a M /
e o e 6
/
l s
f o H 3 mn 0
, d y
i i
h o1 c i a a t
h t
e e
a e c
e P o
h T
o
/ [s t
D tu H
_A t
i t
m S
( ,
2 F
- 0 e 0 n 0 e s P o t
E MH (
/ 1 r
- f o ' -
>7 '
t F
_ e 2 e
h k
s r
8 1
M n
- W o F o
it. d .. 0 0
/'
0 Wx 5 0
F 2 o
V,'
0 i -
0 t d
0 a m
. 5 i e
ps
_ t e p
_ _ s it ar un t
M 2
e t EmH c a f
o g
O ir l
U Z C 0
_ 0 0
0 0 0 a 0 0 0 0 0 0
_ 0 0 0 0 0, 0 0 0 0 0
5 5 0 5 o 0 5 0 5 4 4 3 3 2 2 1 1 c- hm.
-_ mb-
M o
o s
i in h
T i
k o
C l
m s
s o in e o t
h j s T
a e t
3 ) g
/
S 2 p a e 0 u g 0 um m
a A
= B 0 m n ge Y /
0 a o ar 5 D i t
c v e l
e a A 2 u r s F h t
nf F )4 1 t
a on t
l e M 1 ' 0 e of o H 6 r 0 mn1 y 3 ih T
4 h o1 t a r ,
t o
c i e c e t
ew
/
a ah e H _
t D,P o t
A i mS (
t s
3 d t 0
P F( 0 E M 3 r
o
/
f
- t
- e 0 e 0
- h 8 1 0 s 0 k W 2
r n o F e W t s
/V 0 d
_ F 0 2 im 2 O 0
0 t a d 0
5 n 0 0
a 1
t a p s u lt M
2 e Nt E H d
a e
_ c O a la U rC 0
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5 0 5 0 5 0 0 5 5 4 4 3 3 2 2 1 C~ hm-1
M 0
0 0
1 dr i
h T
m 0 0
J c 9 0
0 8
s dr i
h
/
t e T a o t 7 g 0 S 1 p
) i r 0 e 7 e 0 u v g 0 mu A a = B m ne a og a 0 D i t
c ev r l' 0
6 l
aA 2
t e
u F )4 n fof 1 t
r F sh a no t
dr d1 /
e o H eM h 0
0
]JLm
[ n2 o1 y3 6 T 5
//
h a ,r c i t
t e ce %
t a ah e ew t
mS (
D,Po 0 A i t 3 dt l 0 4
s P F E
/'
r M(
f o
t F 0 e 0 0 3
e 0 h 3 1
s
/7 t
k a r n o F it o 0 W 0 n d i
s 0 2
p 9 x g
9 O t
a d n
A a
g ^
p t
0 0
t 1 a
g L. H E
e d
c la g i Z C r
O 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5 0 5 0 5 0 5 0 5 5 4 4 3 3 2 2 1 1 e- -
f
M
_ 0
_ 0
_ 2
_ 1
)r d'
/
- 0 j
_ 0 0
1
_ d ir h
_ T _
s e e g t a a r e
_f t 3 ) v _
S 1 A _
e 0 0 g
a m
0
=
n 0 Ws
)
0 8
D l
a e
i t
o*
c aA 8
/ -
2 uF) F r
) /
t nf e of mn3 4
1 o
t H
a e
dr ih i
t o
' f ' 0 0
6 y
/
h o1 t a H
c i t e c ta ah e D e
t A t mS ( ,
s i
3 P
s
- E M(
_ r 0 T f
o ,.
0 4
- t e
F 0
h k
e s
r 0
8 1
a
/7- ~
n
_ o F o
it W a M_/
0 d
- F 0 i
! m 0 0
_ 0 2 0 2 0 t d
a n 0
fg 5
t s a e p
. a ll e aa lts b o o
M E mH d
_ 2 e O r U Z i la C 0
0 0 0 0 0 0 a o 0 0 0 0 0 0 0 0 o o 0 0
5 5
4
- 5 3
0 3
5 2
0 2
g n
i 5
t- ju-l l
M
_ 0
_ 0
_ 8
_ 1 l
_ i
_ k I
T W
/ M
_ t
/ .
dr h
- 0 0
4 t
s e
T o
g y 1 t
a 8 i
r e
S 0 p ) v 0 u A 0 e 0 0 mu g l 2
a = B 1 m
a n
o e g a
/
D i
r -
l e
t c
aA r
ev / " 0 0
2 u F sh dr l
0 F )4 1
/ s t t t
o n
] n f e o o 1
f o o HM i
h T /
t m n 4 h o 1 y 3 a
6 H
o
/
er t
c a a i
t e e c e w 0
0 h 8 t
D,Po t
A t i m
s S
(
3 lu P
l F
/' " s E M(
//
r 0
_. f o 0 6
_ F
// #
t e 0
_ e 0
_ h 8 1
s t k
r o
a 1
c
/ 0 0
4
_. F it W
F O
O id a
m >
f' 0 2 C 0
a dn t
0 5
t ma 0 0
- a $ g 2 s it n t
M ,
2 e t E
w es m4 e d I
W
- 0 0
ir la Z C J 0 0 0 0 0 0 0 0 0 0 ,
,0
- 0 0 0 0 0 0 0 0 0 0 5 0 5 0 5 0 5 0 ,
5 4 4 3 3 2 2
- C~ t
.* 1 E
!. Attrehment 3 Protective Boundaries Status Determination (Sheet 1 of 2)
REVIEW each of the three barriers to determine whether the barrier has failed or might l fail.
l Fuel Challenged l
If total injection flow is less than boil off flow If vessel level is at or below top of active fuel Fuel Failed .
If core exit thermocouple are greater than 1200 F If RPV level (MP1) is less than M core height j If core heat up calculation indicates fuel failure If containment shows an increase in H2 concentration RCS Challenged (v
If RCS pressure > the safety relief valve setpoint If feedwater flow (MFW and AFW) = 0.0 (PWRs)
RCS Failed l
If inventory loss is indicated by pressurizer level, reactor vessel level monitoring system (RVLMS), or RPV level (MP1)
If containment pressure and temperature increase If containment sump shows an increase in level without another water source l indicated l
l I
l l
O Level of Use EPOP 4422A Rev.1 STOP THINK ACT REVIEW General 32 of 36
i
'a Att chm:nt 3 Protective Boundaries Status Determination
, (Sheet 2 of 2)
Containment Challenged i
If pressure greater than design pressure If temperature greater than design temperature i If no active heat removal is operating when required (CAR, Containment Spray) l Containment Failed C A UTIO N If radiation levels inside containment are high enough to penetrate containment wads or if containment sump recirculation has been initiated following a LOCA with fuel failures, radiation levels will increase outside containment without a containment breach.
If radiation levels increase outside containment due to a release of radioactivity to s the environment If containment pressure decreases rapidly for no apparent reason i
i 1
ss EPOP 4422A Level of Use STOP THINK ACT REVIEW Rev.1 General 33 of 36
Attachment 4 i
Time Until Containment Failure Estimation
, (Sheet 1 of 1)
/ 1. OBTAIN the most roant containment pressure response from OFIS Display A8 or from the Technical Information Coordinator and linear'y extrapolate the pressure increase. l Clock Timei (TI ) Pressurei (Pi ) psia Clock Time 2 (T2) Pressure 2 (P2 ) psia (T2 > T i )
l DP/DT = (P 2 - P ) / (T 3 2 -Ti ) = (
)-( ) =( )(psi) .
( )-( ) ( )(min)
- 2. DETERMINE the time to the failure pressure l At = (Praii - P2 ) / (DP/DT) = ( )-( ) =( )(min) l ( )
Where Pfailis defined in the following table:
Pressure (psia) MP1 MP2 MP3 Pf ail (lower bound) 103 116.7 111.9 Prail(median) 164 164.7 132.4 At = minutes Clock Time to failure = T2 + At i
O' Level of Use EPOP 4422A ST P THINK ACT REVIEW Rev.1 General 34 of 36
t Attrchmcnt 5 >
Core Cooling Water Rescrves Status Determination
, (Sheet 1 of 2)
O Millstone i Status of Cooling Water Supplies Secondary Water Sunoly AFW supply volumes (gal); OFIS Display shown in parenthesis Thnk f .
. MP2 V ull MP3 Vrull DWST 340,000 (A13)
CST 250,000 (A6) 200,000 (A13)
Estimate the remaining useable volume in the tank (assume 5% not useable)
(Note: CST may be used as an alternate water supply for MP3) ;
V= I'* ""
- Tank Volume - 0.05*V fun = gal.
O
~
Determine flow rate from tank (AFW) = gpm Estimate remaining time to deplete tank = V = min.
(AFW) p b Level of Use EPOP 4422A ST P THINK ACT REVIEW Rev.1 j General 35 of 36 l i
r Attachment 5 Core Cooling Water Reserves Status Determination r%
(Sheet 2 of 2) g
% Millstone >
Primary Coolant Sunnlies RWST Volumes (gal); OFIS Display A7 Tank Volume' .MP2 MP3s Tank Full (V full) 475,000 1,200,000 l At SumpTwitch (Vsw) 47,500 562,800 ,
'"**I V= I
- Vruti = gal.
100 l
Determine total flow rate from tank OFIS Display MP2 MP3 Charging (MP3 only) A5* gpm HPSI/S1 A13 A13 gpm LPSI/RHR A13 A5 gpm Spray A13 A13 gpm Total gpm Estimate remaining time to switchover to sump recirculation l
Remaining time to svitch = V - Vsw = min.
l Total Flow
- Note: When charging is aligned for Safety injection, OFIS will show 0 gpm.
1 Ln iv EPOP 4422A t
- Level of Use l STOP THINK AC,T REVIEW Rev.1 General 36 of 36
,