ML20234D602
| ML20234D602 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/31/1987 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20234D581 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8801070105 | |
| Download: ML20234D602 (9) | |
Text
-
0 4
ATTACHMENT 2
TECHNICAL SPECIFICATION AND UPDATED BASES 8801070105 371231 PDR ADDCK 05000302 p
PDR 3
INSTRUMENTATION POST-ACCIDENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The post-accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE with readouts on all channels in the control room.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
a.
With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3-10, either restore the inoper-able channel to OPERABLE status within 30 days, or be in IIOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
The provisions of Specification 3.0.4 are not appliceble.
SURVEILLANCE REQUIREMENTS 4.3.3.S Each post-accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CIIANNEL CH'sCK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.
CRYSTAL RIVER - UNIT 3 3/4 3-37 Amendment No.
SE u
MLL m
m m
q UEB 2 2 2 2 a
a a
2 1
2 2 2 MNA e
e e
r I NR t
t t
e NAE s
s s
p I HP
/ / /
MCO 2 2 2 2
r e
wo P
l l
F u
F 8
F 5
r N
s s
6 h
O T
0 0
g e g e
+
/
I N
0 2 i h i h H
T E
1 9
s c
s c
t o
t t
8 A
ME p n p n e
t e F e 0 T
EG i
i e
e
- e 1
N RN 0
0 f F f 0
f E
- F 0 0 0 0 0 0
r M
SR s
0 2 2 5 0 0 8 0 5 8 h U
A 0 3 3 1
1 1
5 5 1
2 3 /
R E
0 2
6 R
T M
1 1
0 0 0 0 0 0
0 0 0 1
S N
0 I
1 r
G o
3 N
t I
i 3
R n
O o
E T
M L
I B
N n
r A
O i
o T
M g
t r
i T
a n
N M
o E
M
)
D
)
e g
I e
g l
n n
C g n e i
)
o C
n a
v l
e l
i A
e a R e
o g
e t
r R
L o
n v
a T
u h
c a
e i S
t w
g k b R L d O
a o i n
u a
e r
(
(
T o
s n
P r
e L
H a S w
k R p
u m
r e
a e
m s
l l
e e
r l
T g
e s
e e
g t
a p
n T
e v
v a
s N u
r a
T r
e e
r y
(
o e R N
r l
P L
L o S c
t E
e e
t p o a h M
t v
r r r S t
m m
w g
U a
e o
o o
n u
r d i R
W L
t t
t r
a S e
e H T
x e
a a u e
l h
e S
u g r r
r r
r t
o t
T F t
N l
e u
e e
e e
a o
n n
I F
L s
z n
n n W C e
t y e s i e
e e m i c
m n
t e
r G G G d r
n x
n n
o o
r u
e o i E e i r H P s
m m
m t
t a
g a t
s a
a a
a c
t e
r t
u S
S e
e e
e r
a n
r e
n e C C r
t t
t o
e o
o m
o N R R P S S S B R C C E C 1
2 3 4 5 6 7 8 9 0 1
2 3 1
1 1
1 o:D<rH>
wHsw e*we "
e w4" n
>BC2oEoCe Z 3
i'
l ll
!ll
~
N S
O T
LI N
ET E
NA M
NR E
AB Q R R R R R R H R R R R R R
HI I
CL U
A Q
C E
R E
C N
A L
L I
E V
R U
S N
O I
L T
EK A
NC T
NE M M M M M M M M M M M M M N
AH N
E HC O
M C
I U
T R
A T
R 7
S r
B N
o I
3 I
t L
i A
4 G
n C
N o
E I
M L
L R
E B
O n
r N
A T
i o
N T
I g
t A
N r
i H
O a
n C
M M
o
)
M m
T
)
e g
o N
e g
l n
n r
E g n e i
)
o f
D n
a v
l e
l i
I e
a R e
o g
e t
d C
r R
L o
n v
a e
C u
h c
a e i d
A t
w g k b R L d u
a o i n
u a
l T
r e L H a S w
k R c
S e
r
(
(
T o
s n
x O
p u
m r
e a
e e
P m
s l
l e
e r
l T g e
s e
e g t
a p
n e
T e
v v
a s N u
r a
b T
r e
e r
y
(
o e R N'
r l
P L L o S c
t y
E e
e t
p o a h a
M t
v r
r r S t
m m
w g
m U
a e o o
o n
u r d i R
W L
t t
t r
a S e
e H s
T x
e a
a a
e l
h e
r S
u g r r r r
r t
o t
T F t
o N
l e
u e
e e
e a
o n
n t
I F L s
z n
n n W C e
t y e c
s i e e
e m i c
m e
n t e
r G G G d r
n x
n n
t o
o r
u e
o i E e i e
r H P s
m m
m t
t a
g a d
t s
a a
a a
c t e
r t
u S S e e e
e r
a n
r e
n n
e C C r
t t
t o
e o
o m
o o
N R R P S S S B R C C E C r
t u
e l
2 3 4 5 6 7 8 9 0 1
2 3 N
1 1
1 1
c$ca>M 2M<$ c2wH W w
wiw*
> H C n C B C 3 +c
- n i
ll l
lIil1!!l(ll-
3/4.3 INSTRUMENTATION BASES REMOTE SHUTDOWN INSTRUMENTATION (Continued)
HOT STANDBY of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of Appendix "A",
3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that suf-ficient information is available on selected plant parameters to monitor and assess these variables following an accident.
This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instru-mentation for Light-Water Cooled Nuclear Power Plants to Assess Plant Conditions During the Following an Accident, Revision 3, dated May 1983.
3/4.3.3.7 FIRE DETECTION INSTRUMENTATION The OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.
This capability is required in order to detect and locate fires in their early stages.
Prompt detection of fires will reduce the potential for damage to safety related equipment and is integral. element in the overall facility fire protection program.
In the event that a portion of the fire detection instrumentation is inoperable, the establishment.of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation.is returned to service.
l CRYSTAL RIVER - UNIT 3 B 3/4 3-3 Amendment-No.
i l
ATTACHMENT 3
SUPPLEMENTAL SPECIFICATION 1
l l
l
15.3.1 POST-ACCIDENT MONITORING INSTRUMENTATION SUPPLEMENTAL SPECIFICATION 1
l The post-accident monitoring instrumentation channels shown on Table 15.3-1 shall be operable with readouts on all channels in the control room.
t l
APPLICABILITY l
Modes 1, 2,
and 3 l
l HEMEDIAL ACTION With the number of operable post-accident monitoring channels less than required. either restore the inoperable channel to operable status within 30 days or be in. hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
TESTING REQUIREMENTS i
i l
Each post-accident r.nitoring instrumentation channel shall be demonstrated operabic
.y performance of the channel check monthly and a channel calibration each refueling.
1 l
I l
i O
L
N r
G o
A t
T ar e
n eg SE m
MLL e
a UEB v
e MNA A
A l
A t
I NR 2
2 1
/
/
a
/
s 1
NAE N
N V
N
/
I HP
/
2 MCO 1
r h
/
r s
h b
/
l s
S b
m 0
1 p
1 6
g T
g 0
X N
i 1
0 N
E s
0 5
O ME p
X 0
I EG A
A A
A A
1 1
T RN 0
0
/
/
/
/
/
A UA 0
6 N
N N
N N
0 0
T SR 2
1 N
A E
E 0
0 M
M U
)
R r
)
T o
r S
t o
N c
t 1
I e
c t
e 3
G e
t r
N D
e o
5 I
D t
1 R
y a
O r
p c
r r
E T
a u
i o
o L
I m
k d
t t
B N
i c
n a
a A
O r
a I
c c
T M
w P
B i
i e
o
(
(
n d
d T
r l
o n
n w
N u
F r
i I
I o
r E
s o
o t
l w
D s
l t
t i
n n
F o
I e
a a
a s
o o
l C
r t
c c
o i
i r
F C
P o
i i
P t) t e
A T
d d
i r i) t r
g n
n e
so sr a
e T
n t
I I
v ot oo w
t S
i n
l P c Pt d
a O
d a
n n
a e
c e
w P
l l
o o
V et ee e
d i
o i
i ve vt F
e u
o t
t k
l D l e e
B C
i i
c a
aD y
F s
s o
V y V
c T
r r
o o
l r
p n
p N
o o
P P
D ya yu e
u E
t t
t m tk g
t M
c c
V Y
V ei ec r
r U
a a
R R
R f r f a e
a R
e e
O O
O aP aB m
t T
R R
P P
P S(
S(
E S
S N
I 1
2 3
4 5
6 7
8 9
il
(_
i BASES The operability of these post-accident instruments ensures that
)
sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
This capability is consistent with the recommendations of Regulatory Guide f
1.97,
" Instrumentation for Light-Water Cooled Nuclear Power Plants
{
to Assess Plant Conditions During and Following an Accident",
Revision 3 dated May 1983.
)
i l
_ _ _ _ _ _ _ - - _ _ _ _