ML20236S167
| ML20236S167 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/16/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236S169 | List: |
| References | |
| NUDOCS 8711240263 | |
| Download: ML20236S167 (26) | |
Text
'
a us ff o,
UNITED STATES y
g NUCLEAR REGULATORY COMMISSION g
E WASHINGTON, D. C. 20555
\\...+
PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. DPR-70 1.
The Nuclear Regulatory Comission (the Comission or the ~ NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated May 5, 1987 and supplemented by letters dated September 2, 1987 and
~
October 1, 1987, complies with the standards and requirements'of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and' regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and I
safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; l
D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been l
satisfied.
(
2.
Acc~ordingly, the license is amended by changes to the Technical Specifica-1 tions as indicated in the attachment-to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby i
amended to read as follows:
D P
, (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 84
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.-
FOR THE NUCLEAR REGULATORY COMMISSION Donald C. Fischer for Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 16, 1987 I
l Previously concurred
- 4
- , /f/" /87-PDI-2/PM*
OGC*
PDI-2/D*
2 fB'1en DFischer SHLewis WButler
/j g, 11/03/87 11/05/87 11/16/87
[L -
I j
' (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 84, are hereby incorporated in the' license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION.
/s /
Walter R. Butler, Director Project Directorate I-2 Division of Reacter Projects -I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 16, 1987 i
PDI-2/LA PD N/M OGC dM PDI-2/D M0'Brien DFischer 5 H Lals WButler
.r*
/ /87 lllb/87 y /[787 at //w/87
- L
g--
b i
2 1
I (2) Technical Specifications and Environmental Protection Plan I
r The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 84, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date'of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
c kv Walter R. Butler, Director i
Project Directorate.I-2 Division of Reactor Projects I/II 1
Attachment:
Changes to the Technical 1
Specifications d
Date of Issuance:
November 16, 1987
)
l
'l l
1
.._..-_._.__..n_.---_--_A
fE s
, 4 d
ATTACHMENT TO LICENSE AMENDPENT NO. 84
_ FACILITY OPERATING LICENSE NO.-DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Pages Insert Pages 2-5 2-5 2-9 2-9 3/4 3-9 3/4 3-9 3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28 3/4 3-29 3/4 3-29 3/4 3-30 3/4 3-30 j
3/4 3-31 3/4 3-31 l
5 l
wn
D d
d E
n n
D T
Ro Ro d
E A
E c Ec R
n p
T R
We We E
o o
A Os Os W
c o
R f
P P
O e
l o
2 2
P s
f L
L n
r o
A1 A 1 L
r a
e 0
M M
A e
p p
1 Rt Rt _ M p
- s 6
1 E n E n R
w 2
Ha Ha E
s t
o 1
Tt Tt H
t n
l S
1 s
s T
n e
f E
Dn Dn u
m U
e E o E o D
o u
n L
l R
tR T c Tc E
c r
g A
b tE nE A
A T
t i
V a
nW iW Re Re A
5 g
g n
e s
s c
iO oO m
m R
0 3
4 E
i oP pP fi fi i
i i
d L
l 1
s s
p t
ot ot f
e e
p p
f.
f B
p tL eL o
x t
t o
o A
p eA SA
%a
%a o
o 5
5 W
A SM M
S O
R hR
- 5. h
- 5. h 0
3 N
N 5
9 T
L t
wE gE 5t 5t 3
1 e
e 1
2 9
8 8
3 3
9 N
L o
oH iH i
i e
e I
A N
LT HT 5w 5w 5 S S
1 i 5 1 O
PTE S
P I
RT h
h D
t t
E i
i N
D T
w w
O E
A I
R p
T R
R R
E o
T A
Ed Ed W
o 1
A R
f Wn Wn O
l 8
T o
Oo Oo P
2 N
f Pc P c d
n r
E o
e e
L n
a e
2 M
9 Ls Ls A
o p
p U
0 A
A M
c s
E R
5 1
M2 M2 R
e w
L T
2 R
R E
s B
S t
o A
N 5
E1 E1 H n
l 1
H H
T r
e f
T_
I Tt Tt e
m e
n n
D p
u n
M T
l R
tR Da Da E
r g
E N
b tE nE Et Et T
s t
i T
I a
nW iW Ts T s A
t g
g n
e S
O c
iO oO An An R
n 1
2 i
i i
d s
s Y
P i
oP pP Ro Ro u
S T
l p
t-c c
f o
e e
p p
f f
s s
E p
tL eL f
f o
c t
t P
S p
eA SA oe oe o
o 5
5 o
o I
A SM M
m m
N N
6 8
R P
R hR
%i
%i 5
0 8
3 2
0 T
I t
wE gE 5t 5t 2
1 e
e 1
2 9
9 R
o oH iH R
T N
LT HT ia 5a 5
5 S S
1 5 5 1 e
e O
T C
AE h
R n
g o
x i
x x
x r
u w
g h
H u^
u u
t l
l o
i l
l u
F F
F F
e L
H l
e N
n v
n n
n o
e e
e p
o o
o r
r r
L i
r re re e
t T
u u
r t
tt tt g
u A
s s
r T
u ua ua n
e e
eR eR a
N e
e e
t s
s e
r N
N N
R r
r r
a o
e e
u P
P W
t
,v
,v e
e t
T w
T c
e ei ei t
g a
A r
r r
o I
a g
gt gt a
n r
e e
e l
N e
n ni na i
a e
r z
z z
F U
R a
as ag d R
p e
t i
i R
Ro Re e
L l
m w
r r
r f
P N
s A
a r
e e
o e
u u
o r
r i
N u
e eh eh ex r
r r
s s
s s
r c
t p
s s
s O
n w
wg wg t u u
e e
e e
e s
I a
o oi oi nl o
v v
r r
r o
T M
P C
PH PH IF S
O O
P P
P
'L N
U 1
2 F
3 4
5 6
7 8
9 0
1 2
1 1
1
$gxi ei ]
5 y u, P$
"&E l
l l
c n
i a
m h
g a
t n
n i
y e
s d
r a
o 9,
m e
9 r
c y
e T
T b
d r
r t
r o
o n
o f
f i
f o
S r
r p
T 0
e e
N F
l l
p I
d l
l i
'9 n
o o
r O
P a
r r
t T
7 t
t E
7 e
n n
d S
5 r
o o
e c
c t
u "T
u P
S t
I a
g g
p R
R r
1 a
a m
)
T E
e l
l o
d 3
R W
p T
c e
N
)
)
E O
m e
e u
O d
I W
P e
r t
t 1
s n
I e
A O
t o
a a
t u
I P
L f
r r
c i
i T
t A
n 2
A e
e n
T i
f L
M g
0 e
e S
d o
N t
A R
a h
h e
n
)
M E
r
=
t t
e C
W o
R H
e r
c "T
(
E T
v 6
y n
o x
U C
1 R
(
H a
K b
i t
e T
T T
F D
a E
g d
d r
t 2
S N
(
e e
e o
N O
D T
n "T
t z
p n
2 I
I 6
E A
i T
K T
e R
se a
i o
E M
A A
r ar r
l l
m L
E T
R u
t eu e
i l
B T
O t
a rt T
n t
r a
A S
N T
t a
ca e
u o
h T
Y a
r nr r
g f
s e
ie o
t S
s S
T p
p f
nn ns n
I t
3 A m
7 rm oo ac a
A n
P I
3t e
oe F
ii t e r
i R
+
d t
e ft tt ss t
l o
T l
e c
/
ca n
l p
t e
n F e 9
ns o0 e
a R
a g
e
- g 1
un c1 c
p O
c a
r 1
fe a
r i
M.
/ a e
l o
r m=
T 5
i r
e 2r 0
p p
f t
C K
d e
f
- 0. v 0
em e
A n
v e
ho i 3 a E
4 I
A R
1 0a 0
Tc TT L
0 m
R K
u
[
m i
T x
A
=
=
=
=
=
=
=
=
=
=
am 3g3
)
3 I
s 4
6 5
T T
T "T
K K
K 1
S A
t A
A 1
(
l 2 e n r
f ne e
nc w
a r he o
p e
cp r
r e
e e1 v
h h
O w
T 3 2
3 e
e t
t o
o N
N g
gZ~
4 yg o.l* 2.
l x
u E
E f
E s
E E
f l
E L
s L
s i
L d
L s
s L
M B
d R
d B
B n
B d
d B
n I
A n
A n
A A
o A
n n
A ot T
C o
C o
C C
c C
o o
C rs I
c I
c I
I e
I c
c I
E L
e L
e L
L s
L e
e L
t r S
P s
P s
P P
P s
s P
ef ui N
P P
P P
5 P
P n
O A
P 5
A 5
A A
7 A
0 0
A f
S T
0 T
0 T
T 5
T 2
2 T
heo E
O O
O O
O O
tt R
N 1 N N
N 1 N
<- 1 N u
f p S
on M
i E
e 4
T mr I
io E
t S
t N
eu O
sp P
nt S
ou E
po R
s er N
R o O
t I
c T
.e gt A
2 T
ne e
N id E
t 3
M sm
'3 eo t
R t r E
T f
S e
L B
N md A
I ie T
t r M
u E
es T
sa S
ne Y
om S
pse P
x.
eb I
u r
R l
l T
F ml h
oa R
n g
rh.
o x
fsl f
O x
x x
r u
w g
tl n h
H e
T u
u u
t l
C o
i pen l
l l
A u
F l
H l
mna F
F F
e e
enh E
N n
v x ac R
n n
n o
1 e
e e
eh p
o o
o r
r r
l i
r re re e
t A
cn r
t tt tt g
u s
s r
re u
u e
i T
u ua ua n
e e
eR eR a
N e
e e
t t n s
s e
aht r
N N
N R
r T
r r
a s
e o
e e
u t
,v
,v e
e t
P P
W rf n A
T c
e ei ei t
g a
r r
r t
p ooo I
a g
gt gt a
n r
e e
e cnm l
R a
as ag d R
p e
t t
i ti c N
e n
ni na i
a e
r z
z z
eoo t
L R
Ro R e e
m w
r r
r et l
P N
m e
e o
u u
u drc R
a r
r r
r c
t p
s s
s oi N
u e
eh eh e
r r
r s
s s
npn 0
n w
wg wg t
u e
e e
e e
o o
1 a
o oi oi n
o v
v r
r r
rl r T
M P
PH PH I
S O
O P
P P
tat C
M unc I
0 1
Nil ege F
1 2
3 4
5 6
7 8
9 1
1
- se ne kee
"
- w*
R2% 5. E i.
y*
lff 4
/
TAB LE 3.3-5 ENGINEERED SAFETY FEATLRES RESPONSE ITEMS INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 1.
Manual a.
Safety Injection (ECCS)
Not Applicable Feedwater Isolation Not Applicable Reactor Trip (SI)
Not Applicable Containment Isolation-Phase "A" Not Applicable Containment Ventilation Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable Service Water System Not Applicable Containment Fan Cooler Not Applicable b.
Containment Spray Not Applicable Containment Isolation-Phase "B" Not Applicabie Containment Ventilation Isolation Not Applicable' c.
Containment Isolation-Phase "A" Not Applicable Containment Ventilation Isolation i
Not Applicable d.
Steam Line Isolation Not Applicable 2.
Containment Pressure-High Safety Injection (ECCS)
- [ 27.0 (1) a.
b.
Reactor Trip (from SI) 12.0 c.
Feedwater Isolation
- ( 7.0 d.
Containment Isolation-Phase "A" f,17.0(2)/27.0(3)
- e. Containment Ventilation Isolation Not Applicable f.
Auxiliary Feedwater Purgs 1 60 g.
Service Water System i 13.0(2 )/ 48.0(3)
SALEM - 0MIT 1 3/4 3-27 Amendment No. 84 4
n
.s
_TABLI 3.3-5 (Continued)
ENGINEERED SAFETY FEATLRES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECGN__OS -
. 3.
_ Pressurizer Pressure-Low r
Safety Injection (ECCS) a.
1 27.0(1)/12.0(2) l b.
Reactor Trip (from SI) 12.0 c.
Feedwater Isolation 1 7.0 d.
Containment Isolation #hase "A" 1 18.0(2)
\\
Containment Ventilation Isolation e.
Not Applicable f.
Auxiliary Feedwater Pugs 1 60 g.
Service Water System 149.0(1)/13.0(2) 4.
Differential Pressure Between Steam Lines-Hioh Safety Injection (ECCS) a.
1 12.0(2)/22.0(3) b.
Reactor Trip (from SI) 1 2.0 c.
Feedwater Isolation
< 7.0 d.
Containment Isolation-Phase "A" 17.0(2)/27.0(3) l Containment Ventilation Isolation e.
Not Applicable f.
Auxiliary Feedwater Pugs 160 g.
Service Water System 1 13.0(2)/48.0(3) 5 Steam Flow in two Steam Lines - High Coincident with Tava --Low-low a.
Safety Injection (ECCS) i 15.75(2)/25.75(3) b.
Reactor Trip (from SI) 1 5.75 c.
Feedwater Isolation i 10.75 d.
Containment Isolation-Phase "A" 120.75(2)/30.75(3)
Containment Ventilation Isolation e.
Not Applicable f.
Auxiliary Feedwater. Pumps
< 61.75 g.
Service Water System 1.15.75(2)/50.75(3) h.
Steam Line Isolation i 10.75 SALEM - UNIT 1 3/4 3 28 Amendment No. 84
- \\
l a
(
TAB LE 3.3-5 (Continued)
ENGINEERED SAFETY FEATlRES RESPONSE TIMES
_ INITIATING SIGNAL AND FUNCTION t,
RESPONSE TIME IN SECONE t
6 Steam flow in Two S_ team Lines-High Coincident with Steam Line Pressure-Low
)
Safety Inject 1on (ECCS) a.
1 12.0(2)/22.0(3) b.
Reactor Trip (from SI) 1 2.0 c.
Feehater Isolation 1 7.0 d.
Containment Isolation-Phase *A*
1 17.0(2)/27.0(3) e Containment Ventilation Isolation e.
Not Applicable f.
Auxiliary Feehater Pumps 1 60 g.
Service Water System 1 14.0(2)/48.0(3) h.
Steam Line Isolation 1 8.0 7.
Containment Pressure--Nich-High t
a.
< 45.0 Cont' inment Isolation-Phase "B" b.
a Not applicable 1
c.
Steam Line Isolation 1 7.0 d.
Containment Fan Cooler 1 40.0 8.
Steam Generator Water level--Hich-High a.
12.5 b.
Feehater Isolation i 11.0 9.
Steam Generator Water L3 vel--law-tow
- a. Motor-Driven Auxiliary Feehater 1 60.0 Pumps (4) b.
Turbine-Driven Auxiliary Feehater 1 60.0 Pumps (5)
SALEM - tmIT 1 3/4 3-29 Amendment No.
84
- e e
e 4
9 9
4
p-a TAB LE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES
_ INITIATING SIGMAl. AND FUNCTION RESPONSE TIME IN SECQNDS
- 10. Undervoltage RCP bus Turbine-Driven Auxiliary Feedwater 1 60.0 a.
Pumps 11.. Containment Radioactivity - High a.
Purge and Pressure Vacuum Relief 15.0(6) i
- 12. Trip of Feedwater Puses
- a. Auxiliary Feedrater Pumps Not Applicable
- 13. Undeholtaoe. Vital gys j
l 1
l a.
loss of Voltage 14.0
- 14. Station Blackout 4
Motor-Driven Auxiliary Feed Pumps 1 60.0 l
l l
SALEM - UNIT 1 3/4 3-30 Amendment No. 84 l
4 9
e
~
- a
_.o _ _
4 3
TAB LE 3.3-5 (Continued)
TAB LE NOTATION (1) Diesel generator starting and sequence loading delays included. Response time lin.it includes opening of valves to estabitsh SI path and atlpinment of discharge pressure for centrifugal charging pumps. SI and RHR pumps.
(2) Diesel generator starting and sequence loading delays not included.
Offsite power available. Response time limit includes opening of valves to i
establish SI path and attainment of discharge pressure for centrifugal charging pumps.
i (3) Diesel generator starting and sequence loading delays included.
Response
l time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
j (4) On 2/3 in any steam generator.
(5) On 2/3 in 2/4 steam generators.
l
-(6) The response time is the time the isolation circuitry input reaches the l
1 solation setpoint to the time the Isolation Valves are fully shut.
l 1
SALIM - UNIT 1 3/4 3-31 Amendment No. 84 i
y'
[sO cec u
o,,
UNITED STATES NUCLEAR REGULATORY COMMISSION e
rp WASHINGTON, D. C. 20555
~%*...+/
PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY t
DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-31'1 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 56 I
License No. DPR-75 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found -
l that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light
.i Company and Atlantic City Electric Company (the licensees) ' dated' May 5, 1987 and supplemented by' letters dated September 2, 1987 and October 1, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act). and the Comission's rules and regulations set forth in 10 CFR Chapter. I; B.
The facility will operate in conformity with the application, the l
provisions of the Act, and the rules and regulations of the l
Comission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; Land I
l E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
. (2) Technical Specifications and Environmental' Protection Plan l
The Technical Specifications contained in Appendices A and B, as j
revised through Amendment No. 56, are hereby i. incorporated in the i
license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Donald C. Fischer for Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 16, 1987 1
Previous y concurred
- PplL y
PDI-2/PM*
OGC*
PDI-2/D*
MMk aftn DFischer SHLewis WButler
/
/87 11/03/87 11/05/87 11/16/87
n
., u
+
-lA.'
f (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contairied-in: Appendices A and B,;as l
revised through Amendment No. 56-, are hereby incorporated in the~..
license. -The licensee shall operate.the facility'in.accordance with the Technical Specifications.
3.
-This license amendment is effective as of its date of <issuanceb FOR THE NUCLEAR REGULATORY COMMISSION
/s/.
i Walter R.- Butler, Director:
Project Directorate I-2 Division of. Reactor Projects I/II
~
Attachment:
Changes to the Technical Specifications Date of Issuance: November 16, 1987 d
l
.i 1
i 1
l h
1
.PDI-2/LA P
h PM
'0GC2k WButler -
PDI-2/D M0'Brien DFischer s' RL;r a y. -
p (s
/;'/87 ti / 3 /87'
///f/87_
11 /t W87..
--.-.._--...A_-----.-----
.o.
i 2-i (2) Technical Specifications and Environmental Protection P13n The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 56.., are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of-issuance, l
FOR THE NUCLEAR REGULATORY COMMISSION i-
)pa.$k 0, A
Walter R. Butler, Dirdctor Project Directorate'I-?
Division of-Reactor Projects I/II
Attachment:
Changes to the Technical Specifications l
Date of Issuance:
November 16, 1987 1
J i
9 9
9 m_...
-.-_____.m.._.
u
c-n 1
i 1
ATTACHMENT TO LICENSE AMENDMENT NO. 56 I
FACILITY OPERATING LICENSE NO. DPR-75 j
l DOCKET NO. 50-311 j
Revise Appendix A as follows. Asterisk pages are provided to maint.ain document completeness.
Remove Pages Insert Pages 2-5 2-5 2-9 2-9 3/4 3-9 3/4 3-9 3/4 3-28 3/4 3-78*
3/4 3-29 3/4 3-29 3/4 3-30 3/4 3-30*
3/4 3-31 3/4 3-31 3/4 3-32 3/4 3-32
n n
D T
Ro Ro d
E A
E c E c R
n p
T R
We W e E
o o
A Os Os W
c o
R f
P P
O e
l o
2 2
P s
f L -
L n
r o
A1 A1 L r
a e
0 M
M A
e p
p 1
Rt Rt M
p s
6 1
En E n R
w 2
Ha Ha E
s t
o 5
Tt Tt H
t n
l S
5 s
s T
n e
f E
D n Dn u
m U
e E o E o D
o u
n L
l R
tR T c Tc E
c r
g A
b tE nE A
A T
t i
V a
nW iW Re R e A
5 g
g n
e s
s c
iO oO m
m R
0 3
4 i
i i
d E
l oP pP fi fi L
i p
t ot ot f
e e
p p
f f
1 s
s B
p tL eL o
x t
t A
p eA SA
%a
%a o
o W
A SM M
5 5
3 N
N 5
9 o
o 5
5 S
O R
hR
.h
.h 0
T L
t wE gE 5t 5t 3
1 e
e 1
2 9
8 8
3 3
9 N
L o
oH iH i
i I
A N
LT HT 5w 5w S
5 S S
e e
O T
1 5 5 1 P
E S
P I
R T
h h
D t
t E
i i
N D
T u
w O
E A
R p
I T
R R
R E
o T
A Ed Ed W
o 1
A R
f Wn Wn O
l a
T o
Oo Oo P
2 N
f Pc P c d
n r
E o
e e
L n
a e
2 M
9 Ls Ls A
o p
p U
0 A
A M
c E
R 5
1 M2 M2 R
e w
s L
T 2
B S
R R
E s
t o
A N
5 E1 E1 H n
l 5
H H
T r
e f
T I
Tt Tt e
m e
n n
D p
u n
M T
l R
tR Da Da E
r g
E N
b tE nE Et Et T
s t
i T
I a
nW iW Ts T s A
t s
s S
O c
iO oO An An R
n 1
2 i
i i
d g
g n
e Y
P i
oP pP No Ro u
T l
p t
c c
f o
e e
p p
f f
s s
E p
tL eL f
f o
c t
t P
S p
eA SA oe oe o
o I
A SM M
m m
0 N
N 6
8 o
o 5
5 R
P R
hR
%i
%i 5
0 8
3 2
0 T
I t
wE gE 5t 5t 2
1 e
e 1
2 9
9 R
o oH iH R
T N
LT HT 5a 5a 5
$ S S
1 1 5 1 e
e O
T C
A E
h R
n g
o x
x x
x r
u w
g i
h H
u u
u t
l l
o i
l l
u F
F F
F e
L H
l e
n N
n n
n o
e v
p o
o o
r mLe i
r re re e
t T
u u
r r
t tt tt g
u A
s s
r T
u ua ua n
e e
eR eR a
N e
e e
t s
s e
r N
N N
R r
r r
a o
e e
t u
P P
W
,v
,v e
e t
T w
T c
e ei ei t
g a
A r
r r
o I
a g
gt gt a
n r
e e
e l
N e
n ni na i
a e
r z
z z
F U
R a
as ag d R
p e
i i
i R
Ro Re e
L l
m w
r r
r f
P N
m e
e o
u u
u o
A a
r r
r r
c t
p s
s s
N u
e O
n w
wg wg t u u
e e
e e
e s
eh eh ex r
r r
s s
s s
I a
o oi oi nl o
v v
r r
r o
T M
P C
PH PH IF S
O O
P P
P L
N U
1 2
F 3
4 5
6 7
8 9
0 1
2 1
1 1
Et9 8 c5]
7 u.
g uo
,s l'
1 l
lI!li I
~
n c
n a
i a
h m
h t
g a
t n
n e
i y
s d
e r
r o
a o
m e
M m
a r
y c
y e
T T
b b
d t
r r
t r
o o
n n
i o
f f
i f
o op S
r r
p T
0 e
e p
N F
l l
p I
d l
l i
i O
'9 n
o o
r r
P a
r r
t t
T 7
t t
E 7
e n
n d
d S
5 r
o o
e e
t u
c c
t P
t T
u u
I a
g
'g p
p R
R r
a a
m m
)
T E
e l
l o
o d
]
R W
p T
c c
e N
)
)
E O
a e
e u
O d
I W
P r
t t
1 s
s n
I e
A O
t o
a a
t t
i T
u
(
P L
f r
r c
i i
t A
n p
A n
T i
f L
M p
e 0
e e
S d
d o
N t
A R
a h
h e
e C
E n
)
M E
r
=
e e
t t
(
M o
R H
e r
c c,
"T U
C E
T v
6 y
n o
x x
1 R
(
H a
K b
i t
e e
T T
T F
D a
2 S
N
(
E g
d d
r t
t N
O D
T n
e e
e o
o 2
I I
6 E
, A i
T t
z p
n n
T K
T e
R se a
i o
E M
A A
r ar r
l l
l L
E T
R u
t u
e i
mt l
m l
B T
O t
a T
n t
a a
A S
N T
t a
ca e
u o
h h
T Y
a r
g nr r
g f
s s.
S S
T pe ie o
t.
s a
P 3 A m
T, p
f nn ns n
l t
t rm oo ac a
a n
n I
3 e
oe F
ii te r
i i
R d
t e
ft tt ss t
l o
o T
[ e c
/
ca n
l
'p p
t t
e n
m.
M a e
9 ns o0 e
a R
a g
e g
1 un c1 c
p p
O c
a r
1 f e a
r i
i T
5 i
r e
2r 0
p e
l o
r r
- 0. ve 0
em m=
C K
d e
f p
f t
t A
n v
e ho i 3 a E
4 I
A R
1 0a 0
Tc TT L
0 m
ne R
K u
i
[
m m
i i
T x
x A
=
=
=
=
=
=
=
=
=
=
a a
m m
1 3
)
T T
T "T
4 5
6 5
3 3
I_
s s
K K
K 3
t S
a A
A 1 p
(
l t l t r
2 e n en f~
ne ne e
nc nc w
a r ar o
h e he p
e cp cp r
r e
e e1 e0 v
h h
h O
w T3 T3 2
3 4
e e
e t
t t
o N
o o
N N
gE g"
o
?
Eg E
..t i
l ll!
I
e l
x u
E E
E E
s E
E f
l E
L s
L s
L L
d t
s s
L M
R d
R d
B B
n R
d d
R n
I A
n A
n A
A o
A n
n A
ot T
C o
C o
C C
c C
o o
C rs I
c I
c I
I e
I c
c I
E L
e L
e L
L s
L e
e L
t r ui S
P s
P s
P P
P s
s P
ef N
P P
P P
5 P
P n
O A
5 A
5 A
A 7
A 0
0 A
f P
eo S
T 0
T 0
T T
5 T
2 2
T h
E O
O O
O O
O tt R
N
$ N N
N N
<~ <
N u
~
f p S
on E
i M
e I
mr T
io t
E t
S eu N
s p O
nt P
ou S
po E
s R
er R o N
t O
c I
.e T
gt A
ne 2
T id N
t 3
E sm M
eo 3
l t r R
f E
T e
L S
md 8
N ie A
I t r T
u M
es E
sa T
ne S
om Y
p S
se P
x eb r
I u
l l
R ml T
F
'h oa g
rh.
n R
o x
i f sl O
x x
x r
u w
g tl n h
H e
T u
u u
t l
a i
pen C
l l
l u
F L
H l
mna A
F F
F e
e enh E
N n
v xac R
n n
n o
T e
e e
eh p
o o
o r
r r
l cn i
r re re e
t A
u u
e i
r t
tt tt g
u s
s r
re T
u ua ua n
e s
s e
aht e
eR eR a
N e
e e
t t n r
N N
N R
r T r
r a
s e
o
,e e
u P
P W
rfn A
ooo t
v
,v e
e t
T c
e ei ei t
g a
6 r
r r
t p
I a
g gt gt a
n r
e e
e cnm N
e n
ni na i
a e
r z
z z
eoo U
R a
as ag d R
p e
t t
i tic R
Ro Re e
m w
r r
r et L
l P
N m
e e
o e
e u
drc A
a r
r r
r c
t p
s s
s oi N
u e
eh eh e
r r
r s
s s
npn O
n w
wg wg t
u e
e e
u e
o o
I a
o oi oi n
o v
v r
r r
rl r T
M P
PH PH I
S O
O P
P P
t at C
M unc e ge I
0 1
Mil F
1 2
3 4
5 6
7 8
9 1
1
- se m
Nt j
u ER% 2. tm n
'.}'
t lll ll ll
..a
.+-
.]
O TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES I
INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 1
1.
Manual
-1 a.
Safety Infection (ECCS)
Not Applicable-j Not Applicable j
Feedwater Isolation Reactor Trip (SI)
Not' Applicable Containment Isolation-Phase "A" Not Applicable Containment Ventilation Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable Service Water System Not Applicable Containment Fan' Cooler Not Applicable I
b.
.Not Applicable.
i Containment Isolation-Phase "B" Not Applicable I
Containment Ventilation Isolation Not applicable c.
Containment Isolation-Phase "A" Not Applicab1'e.
Containment Ventilation Isolation.
Not. Applicable d.
Steam Line Isolation Not Applicable 2.
Containment Pressure-High I1) a.
Safety Injection (ECCS) 5 27.0 b.
Reactor Trip (from SI) 52.0 c.
Feedwater Isolation 57.0 d.
Containment Isolation-Phase "A" 5 17.0(2)/27.0(3) l e.
Containment Ventilation Isolation Not Applicable f.
Auxiliary Feedwater Pumps
< 60 l
g.
Service Water System 5 13.0(2)/48.0I3) k i
4 L
SALEM - UNIT 2 3/4 3-28 m__
. _ _ _ _ _ _ _ _ _ _ _ _ = _ _ _ _ __
.x__
1____.
m
_.m.._____m...m._____._.____
TAB LE 3.3-5 (Continued)
ENGINEERED SAFETY FEATlRES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONCE 99 3
Pressurizer Pressure-Low a.
Safety Injection (ECCS) 1 27.0(1)/12.0(2)'
b.
Reactor Trip (from SI) 1 2.0 c.
Feedwater Isolation 1 7.0 d.
Containment Isolation-Phase "A" 3 18.0(2) e.
Containment Ventilation Isolation Not Applicable f.
Auri11ary Feedwater Pugs 1 60
, g.
Service Water System l
3 49.0(1)/13.0(2) 4 Differential Pressure Between Steam Lines-High Safety Injection (ECCS) 1 12.0(2)/22.0(3) a.
b.
Reactor Trip (from SI) 1 2.0 c.
Feedwater Isolation 1 7.0,
~
d.
Containment Isolation-Phase "A" 1 17.0(2)/27.0(3) e.
Containment Ventilation Isolation Not Applicable f.
Aux 111 pry Feedwater Pugs 1 60 g.
Service Water System 1 13.0(2)/48.0(3) 5 Steam Flow in two Steam Lines - High Coincident with Tava --Low-Low a.
Safety Injection (ECCS) 1 15.75(2)/25.75(3) b.
Reactor Trip (from SI) 1 5.75 c.
Feedwater Isolation i 10.75 d.
Containment Isolation-Phase "A" 3 20.75(2)/30.75(3)
Containment Ventilation Isolation Not Applicable e.
f.
Auxiliary Feeerster Pugs 1 61.75 g.
Service Water System i 15.75(2)/50.75(3) h.
Steam Line Isolation S 10.75-SAEM - UNIT 2 3/4 3-29 Amendment No. 56
TABLE 3.3-5 (Continued) 1
{
. f.
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 6.
Steam Flow in Two Steam Lines-High Coincident with Steam Line Pressure-Low a.
Safety Injection (ECCS) 5.12.0(2)/22.0I3) b.
Reactor Trip (from SI) 5 2.0 c.
Feedwater Isolation 57.0 d.
Containment Isolation-Phase "A" 5 17.0I2)/27.0I3)
Containment Ventilation Isolation Not Applicable I
e.
3 f.
Auxiliary Feedwater Pumps 5 60 g.
Service Water System 5 14.0I2)/48.0I3) h.
Steam Line Isolation 5 8.0 7.
Containment Pressure--High-Hiah a.
Containment Spray 5 45.0 b.
Containment Isolation-Phase "B" Not Applicable c.
Steam Line Isolation 57.0 d.
Containment Fan Cooler 5 40.0 8.
Steam Generator Water Level--Hich-High a.
Turbine Trip 52.5 b.
Feedwater Isolation 5 11.0 l
9.
Steam Generator Water Level --Low-Low Motor-Driven Auxiliary Feedwater 5 60.0 a.
Pumps (4) b.
Turbine-Driven Auxiliary Feedwater 5 60.0 Pumps (5) l
(
SALEM - UNIT 2 3/4-3-30
~
l TAB LE 3.3-5 (Continued)-
ENGINEERED SAFETY FEATURES RESPONSE TIMES 1
INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS t
- 10. Undervoltace RCP bus Turbine-Driven Auxiliary Feedwater a.
1 60.0
{
Pumps
- 11. Containment Radioactivity. High Purge and Pressure Vacuum Relief 15.0(6) a.
Not Applicable I
{
~
- 13. Undervoltage. Vital Bus I
a.
Loss of Voltage f
14.0
- 14. Station Blackout
- a. Notor-Drivon Aux 111ary Feed Pusps.
< 60.0 i
SALEM - UNIT 2 3/4 3-31 Amendment No. 56 i
i I
_n_
O
TABlf 3.3-5 (Continued) l TABif NOTATION i
(1) Diesel generator starting and sequence loading delays included.
Response
time limit includes opening of valves to establish SI path and att/1,nme discharge pressure for centrifugal charging pumps, $1 and RHR pugs.
1 (2) Diesel generator starting.and sequence loading delays not, included.
l Offsite power available.
Response time limit includes opening of valves to establish $1 path and attainment of discharge pressure for centrifugal charging pumps.
(3) Diesel generator starting and sequence loading delays included.
' time limit includes ope i
Response
n ng of valves to establish SI path and attainment of discharge pressure for centrifugal charging pugs.
e l
(4) On 2/3 in any steam generator.
I I
(5) On 2/3 in 2/4 steam generatorsI
. (6) The response time is the time the isolation circuitry input reaches the
\\
isolation setpoint to the time the Isolation Valves are fully shut,
)
l i
SAIDI - tal!T 2 3/4 3-32 Amendment No. 56 l
O g
e a
4 e
e e e
e e e
a en e e e
e ee
____-.--_w--"~~^