ML19256F029
| ML19256F029 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/15/1979 |
| From: | Kelly R GEORGIA POWER CO. |
| To: | Thomas C NRC - TMI-2 BULLETINS & ORDERS TASK FORCE |
| References | |
| NUDOCS 7911200585 | |
| Download: ML19256F029 (103) | |
Text
4.
Georg:a Pcwer Corrpany g
230 Peachtree Street Post Off.ce Box 4545 At:artt. Georg a 30302 Telepnone 404 522-6063 i
R. J. Kelly Georeia Power Vice Pres; dent and General Manager v
Power Generaton
,re Sognen emnc system November 15, 1979 Mr. Cecil 0. Thomas Bulletins & Orders Task Force U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 SYSTEM INFORMATION FOR B&O TASK FORCE LONG-TERM PROGRAM EVALUATION Gentlemen:
Requests for information on plant systems required for the Nuclear Regulatory Commission's (NRC) staff generic report on boiling water reactors (BWR) were transmitted by your letter of July 13, 1979. The desired date for response to those requests was deferred to November 16, 1979, by Mr. D. F.
Ross, Jr. in his letter of July 26, 1979, to the General Electric Operating Plant Owners Group. Georgia Power Company hereby submits its responses to those requests as the enclosure to this letter. This information is presented in the general format developed on behalf of the BWR Owners Group to simplify regulatory review and the eventual incorporation of the material into generic documents.
If you have any questions or comments concerning this material, please contact this office.
Very truly yours, R. J. Kelly I
WEB /mb
~
Enclosure
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PLANT HNP UNIT (S) l E 2 BYPASS CAPACITY Plant Steam Bypass Capacity, % Rated 25 1375 318 0
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s PIANT ENP UNIT (S) 1 AND 2 SYSTEM AND C0KPONENIS SHARED BEIVEEN UNITS CAPABLE OF PROVIDING POST-ACCIDENT AND TRANSIENT CORE COOLING PAGE FINAL CONTINUED PAGE Single-unit plant check here and do not complete Shared Between System or Component Units Numbers EMERGENCY DIESEL GEN 1B 1 and 2 PIANI SERVICE WATER INTAKE STRUCTURE I and 2 MAIN CONTROL ROOM 1 and 2 CABLE SPREADING ROOM 1 and 2 DEMINERALIZED WATER MAKE-UP SYSTEM 1 and 2 1375 319 I
PLANT NNf UNIT (S)
[ # c'2-PLANT-SPECIFIC SYSTEM INFORMATION General Water Sources Instrumentation
..and Control Frequency of Safety Seismic Safety Seismic Safety Seismic System and System Classification Category Classification Category Classif. Category Component Tests 1.
RCIC 2.
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closed shall be demonstrated OPERABLE by moving each control rod at 8
least one notch At least once per 7 days when above the preset pesor level of e.
8 the Rnst and R$C$. or b.
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- ve of the Rnst and R$CS and three or more control rods are temov.
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2 G. VIA RilR SYSTEt4 HEAT EXCHANfnERS.
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PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE $ CONTINUED ON PAGE ABBREVIATIONS Isolatfon Signal Codes (utility supply)
Engineered Safety ' Function Isolation Valve Type N = NO B
= Butterfly Code Parameter (s) Sensed Set Y = YES BCK = Ball check or Group for Isolation Point (units) ffy
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k gp e
DRYWELL PREBS - HI 2 PSIG D = Direct Control Valve O
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MsL to PRESS 825 PSIG N = Hone GT = Gate
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__r MSL TeuuCL 1EMP HI 200 v CON DEN S ER VAC LO 78 Ha VAC a
SCV = Stop Check I
Tuta SLOG MS L PIPE Fluid SV = Solenoid 2 88 -
-A = Air VB = vacuum Breaker S = Steam XV = Explosive
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REFUELING AEEA V ENT W = Water Others stated in Table ExH RADIATsoN HI 20""/hr Isolation Valve Location Isolation Valve Power Source L
RWCU A Flow HI 79 GPM
"
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"O' I = Inside Containment A
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RW CU AREA VENf' 6T M1 76*F O = Outside Containment AC = AC P
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= Hand Q
Hpc STM supply paEss.to too psio Isolation Valve Actuation Mode _
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HPCI EQUIP RM TEMP M t 175 *F P = Overpressure T
roRU.S AREA AMBIENr I;
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RM = Remote Manual u
renos ARE A virarr A7 ui An'r Others stated in Table
'I V
HDCI EQUIP RM GMER G.
3 Isolation Valve Positions Isolation Valve Actuator AREA coot.ER TEMP Ht i 75*pr A0 = Air W
RCic STM LINE Flow Hi 3ao% OF RAfrD AI = As is Motor X
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PLANT #NP UNIT.5 0
PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE f]}@.00stilNUED ON PAGE j
ABBREVIATIONS Engineered Safety Tunction Isolation Valve Type Isolation Signal Codes (utility supoly)
N = NO B
= Butterfly Code Parameter (s) Sensed Set Y = YES BCK = Ball check or Group for Isolation Pofht(units)
[g",'$c#[3 Position Indication in Control Room C
k g
onywctL pntaS - HI 2 PSIG D*= Direct Control Valve O
MSL HI RADIATION SXFUn PWR SkGRND I = Indirect GB = Globe E
M SL Hi FLOW I40% OF RATED M = None GT = Gate G
MSL IulmEL 1EMP HI 2oO 'F Others stated in Table RV = Relief H
CONDENRER VAC LO 7' Hs VAC s
SCV = Stop Check I
WE8 SLDG MS L PIPE Fluid SV = Solenoid "I
200 *F A = Air VB = Vacuum Breaker S = Steam XV = Explosive
" * " ' ^ ' ' "
'O "#h "
Others stated in Table W = Water K-REFUELING AREA VENT Gthers stated in Table EXH RADIATsoN H 2O"/hr Isolation Valve Location Isolation Valve Power Source L
RWCU A Flow HI 79 GPM
" " U " #"## ## # "'
0' I = Inside Containment A
= Air w
Rwco AREA vent AT us 76 F 0 = Outside Containment AC = AC P
uma sru uME FLOW M.300M OF MATED DC = DC Others stated in Table H
= Hand Q
upct STM suppLv onEss.to too psia Isolation Valve Actuation Mode P
= Process fluid R
upC I TUR B Er H DIAPMR AGM t
Others stated in Table PRESSUR E Hi 10 PSIG A = Automatic S
,j OP = Overpressure T
ronuM AREA AMBIENT
- b)
RF = Reverse Flow TEM P Ht e
l 75og RM = Remote Manual o
ronus AarA vrur AT ni so r 1
a Others stated in Table Isolation Valve Positions Isolation Valve Actuator g4
, ",,"""" f f M*F pH
~. AI = As Is A0 = Air W
RCic STM LINE CLOW HI 360% OF RAfd'D
.C C = Closed M0 = Motor X
RCIC STM uNE PeESS LO SO PSIG 50 = Solenoid Y
RCIC TtlRB ExH DIAPHRAGM 0 = Open Others stated in Table Others stated in Table PREssoRe Hs o Pste s.,
Z GMERG. AREA Co6LER TEMP Mi i 76 'F
~)
- oTM OoME PRESS Ht 135PSIG N
PLANT
\\3 UNIT 2
w A
A
~
3.,
Containment Vent r,
m r,
F010 F002 F120A E
(Fot2)
(F004)
(FlflA)
(Foll )
(F000 (FlioS)
L(F0h 0 )
I (17.15)
(Fol3)
. J J L pog7)
(Fo9I)
(fo8S)
FIGU RE B
A A
m 1
24" F022Aj F02?,A (s) E (8)
(c) 2 (c)
(0) {
(D) 0 gs 2-FOOT b 3 y F025A (F) j g
( K) k*
(P)
(D) 1 I F026A J L (e) cc>
co>
IlGURE C
1377 018
' UNIT 2
PLANT
\\ '
t Containment b
18" Ni y4 F077A FF010A F011A (F081A )[F083A j
)(F082A F084A i
i i
FIGU R E
r i
F038 L
[
QM
[M]
II J2 3"
T, F033 t:
Q F016 F019 y
U$
5 F021
' I F017 m
4 k a
r, u
po2o F034
) 7018 F035 j
l IlGU RE D
1377 019 b-E
PLANT
\\3 UNIT F
e.
A L-N is~
F077B I F010B F0118
] [F0818 Fouas 1
F084B
{F0828 FtGU R F
l Vent ins:de g
4" v,
v, m
F007 l
F008 Containmeat 9 r F036 j g F037 I
FIGU RF G
I
[
j377 020
~
PLANT
\\3 UNIT 2
P J
,a r-'
rd y'
l
[F014
.s I
d F015 g
FIGU R H
p e
e Containment 20" wa w,
es ra n,, ra ra t
-F063j g F064]
)(F083 F143 j
s LF144
,,F084 r
{
b n
l lGURE I
l un 021 e
i P*
t i
PLANT
\\ 3 UNIT f
A@
F050B(A) g 24 J
~
- e F060B%)
A F015B(A)
F017B(A)
F122B(A) 3 y F058B(A) j g i
F128B(A) 1 F059BCA)
] (F127B(A)
FIGU RE J
I I
)[FV008
- g F043A m2 3 y r,
FV007 F027 j g f
6" d 6" Shut,
i s1 Fa
[
Corstainment F002 l
F050 3 r 3 7 m2 F131 F003 i
j g d k 1 7 F0438 j
F006 g
F007]
F132 g
t
[
clGL RE K
k y
1377 022 L
PLANT
\\ 3 UNIT 2
I l
containment l
9 F E B(A)
F002B(4)
F003B(A) 4" H B B w,
w,
l F011B(4) i l
i FIGU E L
i i
6 I
b FYXdB(A) m2 to" 10" mm m,
],
F005B(A)
FfXOB(A)
FUB(Al s
FdB(O
)[F0138(A) 6
)[F100B(M
)(F014B(A)
)
l [noiB(e
,l clGlRF M
i 1377 023 I
i 1
h
1-I
~
PLANT N 3 UNIT 2
l g
Containment g
1
.J 4 ou 1
IS 1 Ia
- Fi48
] ;F0ei
]
F147 F062 I
FIGU RE N
F I
A A
Containment Sy 2
2r t
F020 F019 F018
],(F701
)(F357 l
1 l
P i
IlGURE O
i 1377 024
~
PLANT
\\3 UNIT 2
A A
~
3" MDC m
s 1
li
] [F700
]
]
F505 F856 FIGU RE P
Containment d
F512 F513 9
F651 F589 f
'a F570]
F571[
F590 I
i i
.t IlGURF Q
j 1377 023 F
=
).
[
4 PLANT N3
_ UNIT 2
.,4%
w2 en w2
\\
v, r,
F021 F004 F022 XF083 J.
2,,
2" g,
y F020 m
o F023 F005 F024 JF084 i
FIGU RE R
i k
s~
IS' I,
I r
i a
i I
I I
k e~ b l
i0s2 jf g
F0iO t
3 i
8 a
s 6 t
-lGU RE S
137,/
026 I
I
PLANT N3 UNIT 2
8 f
~
I 2
18,,
.p,
'4$,
]c F307 F308 8,,
i I
--c g
F101 F103
- 1 I
j
)(F009 FD001 u
e e
c e
.d-
}
20" F309 F324 Torus) i i.
L
'P.
f F118A e
g i-f F104 F111 O
Ch m
m V M F1188 l
l F129 I
Torus i
f FIGURE T
.m 027 t'
D' L
a
H,.
l PLANT N3 UNIT f
i i
L a
e r
F --
F341 F340 y
v d '
i I
9 P
[
\\
J k F344 l
f 18" f
N F319 F320 s
s a
i 8"
i FIGU Rr u
5 3
to I
4i 3/4" d
g'.
mm f
F017A(S)
F013A(B)
F014A(S)
)[F084A(B)
)[F085A(B)
] (F001 A(b) i
] [F%2A(S)
IlGURF V
Ul'l 028
,t r
e
PLANT N3 UNIT 2
F l
9 l,
l 3/4~
m2 m2
~
ris is r-s 5
XFas j
t Vet l
l FIGU RE W
i t
TM M
m-
, FI,
N v
w-,
vm i
FM3
.;g l
v J L I
i FIGU RF X.~
i n
I 1377 029
g-.
= =.
i PLANT NP UNIT 2
t M
M 8
b Containment 1sa m
vM y3 F021 A(5)
F016A(B)
]
F036A(S) g FIGU R E Y
i A
-A 1"
m2 m
m r,
r, r,
m F059 F019 EE F020 E
.5 9 P 1 P J L F082 j
j g F021 o
]
I 1083 F022 I.
I i
e l
f, IlGURF Z
r k
PLANT N3 UNIT 2
k J k J r,
r, F003 F004 11/2" N' 1 1/2" DCA m2 r,
F006 F007 F008 E
N NA 9 y R V F040
)[F046 F026g j g F003 F004 j g o
[F041
)[F047
]
F027 g
FIGU RE AA A
A L
2 e
2-r, r,
Er F322 F321 t
A g
(
3 F128 m,
8 r,
u F112B A
A m
m F327 F325 F127 g
Torus i
~
FIGlJRF AB 1377 03I
A,;,.-
l PLANT l-N 3
~ UNIT 2
l C
3 0L F124 F033 F032 f
F034
- Fi47
- Fi40 FIGU R1 AC
, r J L
, r J L L'
~
.T.
6" A
F047 l
l I
i y
,_ L i
u F
F04s i
t
, e l
J L i
, e 4 k clGURF AD ii 1377 032 k
1
& s~
~
i PLANT N3 UNIT 2
i i
i L
,N
(
F851 F852
{
F853
.!3 r
)[F858 6
] [F707 FIGU RE Ar q
I 1" HAR
- q F056 F052 I
F050 F057 (FoSS)
(FOSS)
(F051)
(fos 4) 3
)(F064 (FO63)
)[F0600:059) c I
clGURE Ar r
i 1377 033 6
P
~
PLANT
\\' 3 UNIT 2
~
A A
1" HBB Twi Twi 7_
l F008 s
1"
)[F085 F034
]
F035 T
FIGl] R E AG B
{
f::
2" "ae i
j F335B(A)
F334B(A)
F336B(A) 8 O
F349B(A)
FIGlJRE AH 1377 034 a
~
PLANT N3 UNIT 2
2" HBB 2
r, r,
EF F114 F113 dh 3 p l
F125 m'2 j g 3..
F[12A 8o db
'Ch r,
r, F116 F115 t
Torus 1 P i
pg FIGU RE AJ i
CC i
s[ 6 4"
._2 m
m r,
r, l
g E
F200 F210
.L
[
d
/f;03
' IF214 i
F204) h l
dPs CD Ce F211 F212 i
y F213 I
o l
(Y L
i ClGURE Ar 1
P 1377 035 I-
E.
PLANT N3
' UNIT 2
l Torus i
s E
l
- ,e:
di N
8" F003 F031 F030 F029
[F100 F032 g
g FIGU R AK j
Torus k
O^ 24 sta h.
A,.,
F065C(A,5.D)n F004C(A,B,D)
F030C (A,8,D F132CCA,S,D) i t
t t
i i
j clGURE AL 7
g 3()
F n
ti
t PLANT FN3 UNIT 2
db cn dB n
M ce F3GA(s)
.j M r,
vent (IS}
[F SN l
Torus I
Pressure 60#
9 FIGU R
_AM i
Torus l
.)
/
G-db J2 i
p'001B
[
F 9B (roo A)
(,
g) i 1 IF104B (F104 A)
JL t
L i
clGURE AN 1377 037 e
t-
PLANT N3 UNIT 2
~
'EST
~
TEST 3. ',,. -
n e
~
Y 1 r
.i d
J 6
yo MO
~
F027 F027
~
A B
~
N.d M
^
M s
Mo X211A X211e uo
[
F028 1
$28 8 RHR
W
)M y ( < LOOP B
'MO MO MO E
E FOI2 2E41 A
M B
HPCI M
"2 eM09/7 MIN.
me new
-9
,& f k,Q lL:
[
MO B
FOl9 2E51 RCIC
. ~ -
L
'M I N.
RHR H.X.
2 FLOW RHR H.X.
m THERMAL THERMAL 2
. s c
RELIEF R
RELIEF VALVE VALVE M
d, X224 X2248 8
M D
B A
a.
RHR H.X.
5 8
RHR H X.
VENT
'T' 1'
'T' VENT MO i
MO MO nos aga a n eos A
A B
8 IlGURE Ao
{~"g."g w dy3 m
1377 038 x
s
C.,*
PLANT
\\ 3 UNIT 2
F039A
- F0398 JOCKEY PUMP
/.
SYSTEM p CRW CRW %
~
MO F040B F0128.. r -
Fol2A F040A MO
^~' '
poo4 FOO4 FOO3A A
B FOO3B b
)b RPy.,$d M
CORE SPRAY PUuP l
PUMP
. l.
DISCHARGE r
DISCHARGE MO MO Fol5 FOIS 1
B.
A ua w
r t
rwm n
MO l ~
E l
FO31 F031 A
B C.S.
(
'CS I
P0MP --DC N'
/
D Q-- PUMP 6
NINIMUM F036A F036B MINIMUM l
FLOW FLOW RHR H.X.
RHR H.X.
DRAIN DRAIN MO V
' ~
1 PW d k E 2Eli A^
2 Ell B
4-n
.z MO V
V< uo X226A O
2 Ell A
s-2E X2268
~
RHR PUMP RHR PUMP MINIMUM eV MININUM FLOW FLOW l
JOCKEY F044A F048A F04BB F044B JOCKEY
~
7i?
O W-P P
FLOW FLOW k
V U
.s,
n GU RF AP u
i m+g ag g-un e
.=-
I I
PLANT
\\' 3 UNIT 2
F001 pogo Z
- m
. Torus 1 P i
F041 J L L_
o V
FIGUR AQ.
l L
2" HLB sj w
,L IOM F02$
I Toms i
1 rdass i.
I clGURF AR l.
L
- r..
PLANT
\\3 UNIT 2
~
O m..
M Y-l Torus F021 F049
' IFD003 j g FIGU R E AS 2-
.j l
F040 F022 sr J LF047 Toros i
i D
~
l f
lGURF AT 1377 041 i
s L
w PLANT
\\3 UNIT z
43 db
]
1" mL u-TORUS 2
r, r,
F014 F006 F126A (F 0 IS)
(F007)
(F 1268)
' I I F089 F096
)NF090)
A kg9097) l
\\
t FIGU RE Au A
i
?4 I
F065 F058 F061 IP I IF062 J
Torus F066 A L A L i
r FIGURF AV_
b 1377 042
g.
l
~
l PLANT -
N 3 UNIT 2
I Torus t
F001 8" H LB
)
m2 u
g r,
u a
F002
- :*oo3 y FD002 jg l [F004 FIGU RE AW S
b 18" lsfl lsfl F318 '
F326 l
k f,
2" HBB s
F339 F338 1 P J L F346 g
j l
Torus I
U i
IIGU RE AX l
r I
1377 043 i
~*
~
l PLANT.
\\'3 UNIT 2
S E
4~
i FAAG)
Fb04h(5)
.O l
Torus l
[ F012A(5)
I e
FIGUR AY i
E 9
2" N
m f
FIII F102 F103 F104 L
JF113 X
F114 f
v F112 j g 1
i
~
i t
IlGU RE AE i
1377 044 L
e i
PLANT
\\ 3 UNIT 2
i t
N 11/2" N
>A r,
F105 F102 F103 F104 f
)(F106
)(F107
)(F108 r
6 i
I t
l i
FIGU RE BA r
I t
i
~
I I
2" HBB
&2 m
>Q-r' r,
F393A F333A F332A F337A (a) s)
(3)
(g)
Torus I
)[ F394A(s)
]
F345A(B) f I
}
r I
i i
i
~lGU RE 88
[
1377 045 L
PLANT
\\3 UNIT 2
i l
O I
Torus i
k j,,
m a
3..
a a
m F016 F011 F012
[F015
)(F014 FIGU RE ac FR0M
,a p, *
' m M ST* W T
1 i
excess ri.ous CNec8 vAz.vr l
t i
FIGU RE 80 1377 046 t
66
~
PLANT N3 UNIT 2
O To X37C W l -l l iucrauusur (x 34D)
F0410 (x54C)
(T48-F563 A )
( Fof t O )
cc
. ro x 32,
' tusistuMesJr (X6sO) po4:S
(^ 0+ ^)
(74 &-F36 3 S)
{ Fo4 t A )
FIGU RE s e-m a
f m
e r--> M!
te xt.
(
)
i e
inas
[U2U3 g N3TRUUfUT IMSTR UMc M r
\\
)
2-> =t v
ClGURF 6F 1377 047 D
PLANT N3 UNIT _
2 8
4 sc
's It3,_
~
rm DRIVES r,
a v4 t
FIGU RE Bu 70Ruh
\\
M VI VOSI F042 FIGU RF 6N 1377 048
e PLANT
\\P UNIT f
N-Folo o l=Ib 9 FIGU RE ao FIGURF 1377 049
CEN 72/fuG Al LA 6 ATE VALVE Puu P g
GLOBE VALVE AIR OPER ATOR l
8UTTERFLY l
VALVE I
PCESSUES Q
M OTOR OPERATOR M
2&L IEF VA LVE
&{,,($l0$O
$ll. OE AUG OPERA To IC VA LvE-O e
ElGU RE A
SYMBOLS 1377 050
PIANI HNP UNITS 1 AND 2 DESIGN REQUIREMENTS FOR CONTAINMENT ISOIATION BARRIERS Question: : Discuss the extent to which the quality standards and seismic design classification of the containment isolation provisions follow the recommendations of Regulatory Guides 1.26, " Quality Group Classifications and Standards for Water, Steam, and Radioactive-Water-Containing Components of Nuclear Power Plants", and 1.29, " Seismic Design Classification".
Response
All containment isolation barriers provided for ENP 1 and 2 have been designed, fabricated and* erected to the requirements for seismic category 1 systems as specified and/or implied by Regulatory Guide 1.29.
The quality group classification for the ERP 1 and 2 containment isolation barriers are as specified and/or implied by Regulatory Guide 1.26, with the following exceptions:
A.
The main steam piping to the turbine stop and bypass valves is quality group B, with the exception that the branch lines for the steam jet air ejector motive steam and the turbine steam sealing system are provided with manual isolation valves (as noted in the FSARs) in lieu of remotely operable valves.
B.
Seal and motor cooling water for the reactor recirculation pumps has been provided as quality group D inside containment (as noted in the FSARs) in lieu of quality group B.
C.
Drywell chill water piping (for HNP-2) and Drywell cooling water piping (for HNP-1) have been provided as quality gtoup D (as defined in the FSARs) in lieu of quality group B.
D.
Equipment and floor drain sump pump discharge piping penetrating the primary containment for ENP-1 has been provided as quality group D (i.e. - piping and valves supplied to USAS B31.1.0, with NDT to USAS B31.7) in lieu of quality group B.
E.
All nuclear grade piping systems for ENP-1 are provided in accordance with USAS B31.7, Class I, II or III, as appropriate, 1969 edition, Nuclear Power Piping Code.
1377 051
PIANT HNP UNITS 1 & 2 PROVISIONS FOR TESTING Question:. Discuss the design provisions for testing the operability of
'the isolation valves.
Response
To ensure the integrity of the containment isolation system, preoperational and in-service surveillance testing is performed on the containment isola-tion valves, contairunent penetrations, and control systems for initiating isolation.
The PC/RPV isolation control system is testable during reactor operation.
Isolation valves can be tested te ensure that they are capable of closing by operating manual switches in the main control room and observing the position lights and any associated process effects.
Testable check valves are arranged to verify that the valve disk is free to open and close. The channel and trip system responses can be functionally tested by applying test signals ta each channel and observing the trip system response.
The MSIVs can be functionally tested for operability during plant operation and refueling outages. During a refueling outage the MSIVs can be functionally tested, leak tested, and visually inspected.
The MSIVs can be tested and exercised individually to the 90-percent-open position because the valves still pass rated steam flow when 90 percent open.
The MSIVs can be tested and axercised individually to the fully closed position if reactor power is reduced sufficiently to avoid scram from reactor ovarpressure or high flow through the steam line flow restrictors.
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a PIANI HNP UNITS 1 & 2 CODES, ShNDARDS AND GUIDES Question: Identify the codes, standards and guides applied in the design of the containment isolation system and system components.
Response
General Design Bases a.
Containment isolation valves provide the necessary isolation of the containment in the event of accidents or other conditions f when the free release of containment contents cannot be taisitted.
b.
The design of isolation valving for lines penetrating the containment follow the requirements of General Design Criteria 54 through 57 to the greatest extent practicable consistent with safety and reliability.
c.
Isolation valves, actuators, and controls are protected against damage by missiles, d.
Design of the containment isolation valves and associated piping and penetrations is seismic Category I.
e.
Containment isolation valves and associated piping and pene-trations meet the requirements of the ASME Boiler and Pressure Vessel Code Section III Classes 1, 2, or 3, as applicable for HNP-2 and to the applicable portions of the Nuclear Power Piping Code, USAS B31.7 for EiP-1.
The design and installation of instrument lines is in conformance with Regulatory Guide 1.11 (March,1971), with minor exceptions as indicated below.
Instrument Lines Connected to the Reactor Coolant Pressure Boundary The instrument sensing lines listed below penetrate the primary containment and connect to the reactor coolant pressure boundary.
All lines are equipped with a restriction orifice located as close as is practical to the point of connection to the coolant pressure boundary inside the primary containment. A manual shutoff valve is 1ccated on the outside of the primary containment and is installed as close as is practical to the point of exit. Immediately down-stream of the manual valve is an excess flow check valve which automatically closes for a line break downstream of the valve.
Indicating lights on a ecutrol room panel monitor the valve position.
The valve may b e reopened by action of a solenoid attachment which is operated from the panel after repairs are made. This system ful-fills the requirements of Regulatory Guide 1.11 (March,1971). There are no instrument lines which penetrate both primary and secondary con-tainment.
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b a.
16 lines for sensurement of asin steam flow b.
24 lines for jet-pump flow measurement c.
9 lines for reactor water level and pressure asasurement d.
8 lines for measurement of recirculation-pssp discharge flow 8 lines for jet ;ung header-differential-pressure measurement e.
f.
4 Iines for esasurement of differential pressure across the recirculation pumps 4 lines for asasurement of recirculation-pump seal pressures 3
b.
4 lines for measurement of core differential pressure and reference for jet ptasp flow 1.
4 lines for steam leak detection system for the EPCI tutbine steam line
- j. 4 lines for steam leak detection system for the RCIC turbine steam line k.
2 lines for measurement of recirculation. pump 3 suction pressure 1.
2 lines for core epray header-differential-pressure measure-asnt Instrument Lines Connected to the Primary Contai w t Atmosphere Six lines which penetrate the primary contain= ant are used a.
for measurement of 5, and 0, content ci the primary contain-ment staosphere. Thise lines have two air-operated isolation valves outside of the a.ontainment downstream of a manual shut-off valve. An exceptica to Regulatory Guide 1.11 Olarch 1971) is taken here since both isolation valves are outside the con-tainment; however, installation of a valve inside the rentain-ment would reduce the reliability of the system, and the pur-pose of the system is to monitor the containment atmosphere during and after an accident. The isolation valves have auto-antic isolation which may be overridden by operator action to permit monitoring the contain= ant atmosphere. These valves may be remotely closed by the operator in the main control room. Yalve position indication is also provided in the con-trol room.
flf
6 a.
d b.
Two lines penetrating the primary containment are used by the l fission products monitoring system. These lines are each pro-vided with two air-operated isolation valves outside of the containment downstream of a manual shutoff valve. These valves are closed automatically during sad after an accident but can be manually overridden to permit monitoring the containment atmosphere. The valves any be remotely operated by manual action from the main control roca. Indication lights are also provided in the main control room to show valve positions.
These lines conform to Regulatory cuide 1.11 Olarch 1971).
One line is connected to the torus (pressure-suppression chamber) for fission products monitoring. This line has two manual shutoff valves located nutside the containment.
Two lines are connected to the pressure-suppression chamber c.
(torus) and six lines are connected to the drywell for asasure-ment of containment pressure. Four more lines are connected to the torus for level measurement. In each of these lines, o6e manual isolation valve is located outside of containment and one remotely operated (from the main control room) valve is located downstream of the manual valve. Rach of the remotely operated valves is a fail-as-is type with remote position indication in the control room. An exception to Regulatory Guide 1.11 Otarch 1971) is taken for these lines since, as in case a above, these lines are needed to asasure significant parameters during and after an accident _.
Other Instrument Lines Twelve lines penetrate the torus shall to. supply air to piston operators on the vacuum breaker valves. These instrument lines conform to Regulatory Guide 1.11 01 arch 1971). They do not penetrate the reactor coolant pressure bound-ary nor are they open to the primary containment atmosphere. One solenoid valve is located close to the penetration outside of the torus shall for each line. The valves are manually controlled from the control roca where position indication is also provided.
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D T
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. oo INSTRIMENIATION AND CONTROL DESIGN BASES A.
IEEE 279 Conformance to IEEE 279-1971 is demonstrated in topical report NEDO-10139, Paragraph 4.2.
B.
IEEE 338-1971 The system is testable during reactor operation. The tests which may be performed trill cover the sensors through the final actuators, demonstrate independence of channels, and bare any credible failures while not negating any isolation.
C.
IEEE 323-1971 All Class IE equipment and components were qualified in accordance with IEE STD. 323.1971.
D.
IEEE 344-1971 Veh few of the NSSS, Class IE devices were coupletely qualified by analysis alone. Sometimes, however, besides being used for passive mechanical devices, analysis was used in combination with testing for larger assemblies containing Class IE devices. For instance, a test might have been run to determine whether there were natural frequencies in the equipment within the critical seismic frequency range (see IEEE 344-1971, 3.2.2.3.1).
If the equipment was determined to be free of natural frequencies, it was asstaned to be rigid, and a static analysis was performed as shcwn in Appendix C of NEDO 10678 (see IEEE 344-1971, Paragraph 3.2.3.4).
If it had natural frequencies in the critical frequency range, calculations of transmissibility and responses to varying input accelerations were determined to see whether Class IE devices mounted in the assembly would operate without mal-functioning.
The seismic qualification of equipment supplied to GE by others was required to follow the same procedures as those used by GE.
The qual-ificatiot data were supplied to and reviewed by GE for conformance to the required procedures, g.
Rerulatory Guide 1.22 (February 1972)
The main steam line isolation valves and associated logic and sensor devices may be tested from sensor device to one of the two solenoids required for valve closure. The valve any be exercised closed with a slow-acting taat solenoid to verify that there are no obstructions to the valve stem at full power. A reduction in power is necessary before performing a valve closure using the two fast-acting main solenoids. All the isolation valves, other than the usin steam line isolation valves, may be tested from sensor to actuator during plant operation. The test any cause isolation of the process lines involved, but their isoletion is tolerable.
'i 1377 056
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- D b.
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OS c
F.
10CFt50 Appendix A a.
General Design Criterion 13 The integrity of the reactor core and the reactor coolant pressure boundary is ensured by monitoring the appropriate plant variables and closing various isolation valves, as detailed in the various description sections.
b.
General Design Criterion 20 Protection system functions. The PC/EFV isolation control system automatically isolated the appropriate process lines.
'c.
General Design Criterion 21 Protection system reliability and testability. The high reliabil-icy relay and switch devices are arranged in two redundant divisions and in separate locations. Complete testing may be performed as discussed with respect to Regulatory Guide 1.22 (February 1972).
~
d.
General Design Criterion 22 Protection system independence. Two redundant divisions are physically arranged so that no single failure can prevent an isolation. Functional diversity of sensed variables is utilized.
e.
Genersi Design Criterion 23 Fail-safe design is employed so that loss of power or postulated adverse environments leave the protection system in a safe state.
f.
General Design Criterion 24 Separation of protection and control systems. The system has no control system functions. The equipment is separated from control system equipment te the artent that no single failure in a control system can prevent an isolation.
g.
General Design Criterion 29 There is an extra:nely high probability that no anticipated operational occurrence will prevent accomplishment of safety functions.
C.
10CFR50 Appendix B The CPC Quality Control Program includes the fo11erlag: organization; p1maning; procurriment control; material, equipment, and services control; field fabrication and construction control; test control; document and record control; sad audits. These program elements as applied to the safety-related structures, systems, and components uset the intent of the applicable criteria of Appendix 3 to 10CFR50," Quality Assursace criteria for Nuclear Power Plants."
1377 057
4e -
1 PLANT HATCH UNIT (S). Land 2 NORMAL OPERATING MODES AND ISOLATION MODES Question:
Discuss the normal operating modes and containment isolation provision and procedures for lines that transfer potentially radioactive fluids out of the containment.
Response
Plant systemsIwhich are designed to cause a transfer of potentially radioactive gas or liquid from the primary containment during various modes of plant operation are the purge system vent valves and the radioactive waste collecting sump subsystems.
The purge system vent valves are maintained in the normally closed position through the application of administrative controls during all modes of plant operation. Any time the valves are in other than the closed position an audible and visual alarm is annunciated in the main control room to alert the operator of the abnormal condi-tion. These valves are small bore (2-inch nominal diameter) devices and are employed in four separate penetrations, each penetration having three valves in series.
Thus, to vent gas from the containment atmosphere, the operator must manipulate three specific controls for each penetration. On Unit 1, these valves are used periodically as a normal means of containment pressure control.
During the time these valves are open, an operator is assigned the single duty of monitoring them and manually closing them if a containment isolation signal is received.
Two additional penetrations are provided as a part of the purge system, each employing two 2 inch nominal diameter valves in series for normal plant operational containment venting processes. These penetration valves are provided with containment isolation system automatic closure signals and may be used post-accident by operation of an override interlock switch. In addition, these valves are closed (if open) auto-matica11y upon receipt of high reactor and/or refueling area radiation signals.
The radioactive waste collecting sump subsystems collect and transport normal liquid leakage from the primary containment to the radioactive waste treatment system.
The pump discharge valves are automatically closed by the containment isolation signals. Subsequent to clearing these isolation signals, the valve control circuits may be reset by the operation of the reset switch in the main control room.
As a result of this review and in light of the recent accident at TMI, it should be noted that the reset device for the liquid radioactive waste discharge valves described above is coumon to numerous other devices. Consequently an operator performing the reset function may not recognize the potential for this liquid discharge path to the radioactive waste treatment facility. Upon actuation of the reset, with the valve operating switches in the OPEN position, and assuming sump pump power avail-ability and ptanp operability, the sump pumps will automatically start and transfer liquids (at a rate of approximately 300 GPM) from the containment sumps to the rad-waste building storage and processing tanks.
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dhk Response (Cont'd)
Plant procedures for responding to an automatic containment isolation require that the control switches which operate these valves be placed in the closed position immediately following an automatic isolation signal. Therefore, if the isolation signals are cleared and the system is reset, these valves will not automatically reopen. Any contaminated water in the sumps will remain within the primary containment.
In addition to reliance on the plant procedures in the interim, design changes have been initiated to cause the vent valves to isolate automatically with the ECCS initiation signals, and the radwaste sump pump discharge valves will be provided with suitable circuitry to preclude automatic opening following reset of the isolation signal.
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