ML20084D674
| ML20084D674 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/26/1984 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8405010433 | |
| Download: ML20084D674 (8) | |
Text
'
\\
SOUTH CAROLINA ELECTRIC & GAS COMPANY Post o.ric. 7e4 CotuweiA. South CAROLINA 29218
$ E.'."..".d"'
April 26, 1984 svet... o..uio.
Mr. liarold R. Denton, Director Office of Nuclear Reactor lation U.S. Nuclear Rcgulatory asion Washington, D.C. 20555
Subject:
Virgil C. Summr Nuclear Station Ibcket No. 50/395 Operating Licenso No. NPF-12
'Ibchnica1 Specifications l
3/4.6.1 and Table 3.6-1
Dear Mr. Denton:
In a letter dated Octcher 8,1982, frcxn O. W. Dixon, Jr. to 11. R. Denton, South Carolina Electric and Gas Conpany (SCI %G) requested that Table 3.6-1, " Containment Isolation Valves," be revised to indicate that Type "C" leak rate testing is not required for an additional fourteen (14) containnent isolation valves. By letter dated March 30, 1984 frcxn E. G.
Mensam to O. W. Dixon, Jr., additional infonnation regulred to conplete tin review of this Technical Specification change was requested. As a result of a further evaluation of this proposed 'Ibchnical Specification chango, SCEEG is amending this change request as follows.
Based on the fact that the provisions of 'Ibchnical Specification 3/4.6.4 do not apply to the manual, rennte manual, and check valves listed in Table 3.6-1 and that Type "C" leak rate testing requirenunts are provided in Technical Specification 4.6.1.2, the listing of those valves in Table 3.6-1 is considered 111ustrativo. In an effort to clarify theno technical specifications, it is requested that the MANUE, REM 7FE MANUAL and CIECK valvo sections be doloted from this table, the i signs be dolotul from tin remaining sections of this table, and that the titio of this tablo be changed to " Automatic Containnent Isolation valven."
In addition, it in requestal that the reference to Table 3.6-1 in Technical Specification 4.6.1.1. be doloted and that the notes (1) and (2) at the bottan of Tablo 3.6-1 be conbined and added to Technical Specification 4.6.1.1.
Also, noto (3) at the bottom of Table 3.6-1 should be doloted because it is no longer applicable. 'Ihe above changes are incluid on the attached Technical Specification pages.
SCI %G has determined that a finding of no significant hazards consideration is appropriato in that Technical Specification requirements are only being rearranged and clarified, not changed.
'Ihis chango has been reviewxl and approved by the Plant Safety Review Comnittee (PSRC) and the Nuclear Safoty Review Comnittee (NSRC). Decauso 8405010433 840426 a
', 0M PDR ADOCK 05000395 P
PDH 9
+
1 Mr. Harold R. Denton Technical Specifications 3/4.6.1 and Table 3.6-1 April 26, 1984 Page $2 of the administrative nature of this change, an overpayment in the amount of 'Nenty-Eight Hundred Dollars ($2800.00) was mado for the previously requested change to Table 3.6-1.
Should you have any questions, please contact us at your convenience.
Very truly yours, 3
O. W. D n
AMP /tMO/gj Attachments cca V. C. Sunener C. A. Price T. C. Nichols, Jr./0. W. Dixon, Jr.
C. L. Ligon (NBRC)
E. H. Crews, Jr.
K. E. Nodland E. C. Roberts R. A. Stough W. A. Williams, Jr.
G. Percival D. A. Nauman C. W. Hohl J. P. O'Reilly J. B. Knotts, Jr.
Group Managers NPCF O. 8. Bradham File l
l l
L.
3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STAN08Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hcurs.
$URVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
At least once per 31 days by verifying that all penetrations
- not a.
capable of being closed by OPERA 8LE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions **z::;t 2: ; ;;id:d in idi; 3.0 i ef
';;;ifi nti;; 5.0.'.
b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
After each closing of each penetration subject to Type 8 testing, c.
except the containment air locks, if opened following a Type A or 8 test, by leak rate testing the seal with gas at P (47.1 psig) and verifying that when the measured leakage rate for*these seals is added to the leakage rates determined pursuant to specification 4.6.1.2.d for all other Type 8 and C penetrations, the combined leakage rate is less than 0.60 L,.
"Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUT 0OWN except that such verification need not be performed more often than once per 92 days.
- Manual aml remote manual valves nay be opentxt on an intermittent basia under a&tinistrative control.
SUMER - UNIT 1 3/4 6-1 J
I m
n m
R' O
m n
e r
a m
$2 TABLE 3.6-1 AuTCM ATs c.
COPITAlr#1CN 150LATI0ti VALVES MAXIMUM E
ISOLATION TIME
^g VALVE NUMBER A.
PilASE "A" ISOLATION FUtiCTION (SEC) 1.
7501-AC CRDH Coolant Water Inlet Line 40 2.
7502-AC CRott Coolant Water Inlet Line 40 3.
7503-AC CRD?l Coolant Water Outlet Line 40 4.
7504-AC CRDH Coolant Water Outlet Line 40 40 5.
503A-BD -#-
Steam Generator A Blowdown Line 40 6.
503D-0D -#-
Steam Generator D Blowdown Line 7.
503C-BD Steam Cencrator C Blowdown Line 40 40 8.
8100-CS Reactor Coolant Pump Seal Water Return 9.
8112-C5 Reactor Coolant Pump Seal Water Return 40 10.
8149A-C5 Reactor Coolant To letdown iteat Exchanger 40 11.
81498-CS Reactor Coolant To Letdown lleat Exchanger 40 q
Reactor Coolant To Letdown lleat Exchanger 40 12.
8149C-CS Sp 13.
8152-CS Reactor Coolant To Letdown IIcal Exchanger 40
- g 14 6797-FS rire Service Deluge To Charcoal Filters 40 15.
6050A-IIR flormal Reactor Building Pressure Line 40 16.
6054-l!R tinrmal Reactor Buildino Pressure Line 40 i
17.
2660-IA Reactor nu'ilding Instrument Air Inlet Line 40 10.
2662A-IA Reactor Building Instrument Air Suction Line 40 19.
26620-IA Reactor Building Instrument Air Suction Line 40 20.
6242A-ND Reactor Building Sump Drain 40 21.
62420-ND Reactor Building Sump Drain 40 22.
8028-RC Pressurizer Relief Tank Makeup Water Line 40 Supply-Return Line 40 23.
8033-RC Pressurizer Relief Tank N2 Supply Return Line 40 Pressurizer Reiter Tank N2 24.
8047-RC Full Line To Accumulators 40 40 25.
8860-5I 26 8880-5I Accumulator tiitrogen Supply 27.
8871-5I Accumulator Test Line 40 28.
8961-5I Acctanniator Test Line 40 29.
9311A-55 Sampling line Supply To Radiation Monitor 40 30.
93118-55 Sampling Line Supply To Radiation Monitor 40 6
L
e l
./
u l
l W
_. _O. u O O,O. y,O.,O O O. O. O O O O,O O O.-.C. O. v.:.,O O C
OO C000000 m
e,- :
v.:,: < e v or v
e <:
e eceeoee
> *m 5 <d v O
m me L L O O e ed C C C CC O O E lC 333
- J.c J
O O O em em C c c: c2 u u
- 3 t "p
- es cg c3
.C C
3 33 33 e
..c.c
- . C a c.
ooo c
-=
.J J
cco0 C c
=
L L T
m c.
C coC
- c3 c3 L L >- >=
re to ac c3 y J
==
.J =d J.,J CJ Q L
yy
==
sig c3 y t *= UD r:
C2 C;3 C. C. C.
- r:
.J =J.J
- cc=3 e
ooo C 0:
C C CC L L LU C 6 L c3 eW CC C ccc4 C C O :. :~. C r:
C. O. s.s.s 85 "C C C O @ G G M =J. b uu
"~~
=> &
- J
.;.C eegg LLL C =
{ C.g c c g o.o L L L L L C C Qo6 L L L=
cemmem 0 O u u u u.O U U C &
Q==
=
6w 0
.J.J a
N N J = C C ;> 3m O O.= - -
A6.. r3 og c:
m N
.a*=
b L L L cC C O 6 6 6.
L L L C DQ-OQC.4MXM
. u W ] "'b )g s.
U" =L t
c =, - >=. :s :s =
4.C A
J.J.J =
c==c0eo uu.. u o es a:s
_J CJ a.a J :=cce m m uu u u gE E Etoc: rs e e e o
.czce o o c c O t c m e m es r: c to to es es>=>=>->=
k 6 L 666.
cc CC U CJ U U W U U uU UU CJ G tJ CC ct 8 R u *J -d *J C C
== m - m =*-.C C > > >
c o O >O O
=
0 0L L 6 c:: C: C c:
- - c o tJ ooL Lp - > -
O
>g = - w c. c. c. EGEE r: re r: 4 c: c: cc P= >=L 6.
=
Cs
- 2. = U tJ QGGCO OC Q88GL k L L tJ G U y
a
".s
=
C O C L L L L oC C C Q ::2 O O EC 22 u O O C' t". C.==.0 O Ci.. - 6 6 66666 L L L L O== = *.
w,,' O m :=.J.= 6 6 6 6 6 6 6. =J J.J =J L LL
= =.=..= J J J
.r, eeee c:
O C C Q g
s"
.O t.
2 CO U C GC UQ CD C L c5 r".
c r: " =J.J C C C C 'C *C *&
l
- .c...c..c.=..=...=..=..= =.c = ~ ~ -
u n e.
C ocoou eI
-*C C 0 C L LL uuuuOUC y
.. - =
= '.= " = =J =J =d = = ' =.J. J J =J
==.J =d C C C U CG 666
~
r*. t C
=l s
0 C uV u=CC J *J J J w
- O 0".c
- : O O ""i O Ci O C". C' O O C'.
(J & U
=
C=
==mm
==
= c=L L L -L C C C c tJ ts cs r3 r: rg
......c.=..== * * = 0.C C
==
= = ;:
C C C O VUL g, c. ~ m e e m g:
BBR C C c o w w e.
e m m ee ~ ~.J
.J
.,6 g
og
[ C. F { F F a.
E-E - c. E m e a:
- - - -e v v v v r. c r.
e.
F. '.B aE =.E..c aF a
F
[s r.:
- c. - o
=
u ce C c c-
- c. c. - -
8..: /c. e e J.e: e e d.a.
=
e m :c c: :: r.:... e uvvuvuu y
O
~b 5=
.c O
b C
a u
w
<t*
m
=
O O
I"*
I k-5
~
seses
.s m~
o o
h
[ ')
==
tein14:
==
u > >.m>
>>2 n.
mm m.m m m eme cm vu
~ N m - e o r c: co u u e 6, ce u $. $. $. $. 6 6 u.
- m. m. m m m. m. m m m m m m m. m. m 6
- v. u. u. v.
m cric e i em i
< c: m. m. < es
< e: u w e
- - n.- m e m e e e e co c c, c, e O M e 8 es u p
wmeer.
ca co co c2 w
ca e m e M m M g
wmOMr r.s eOOOmMM eeceee@
M M m M c'1 M M M r'1 M M c*) M M M *=4.=4 Q
.=4 e e. e.
a.
mmme---
g m m m m m m eym m m m m m m er.r
-r.M -
.6 W :-
/
>J
(
.=* N M e:* e @ P%
M M M M M M M M M e e w e v w e e,0..m o ** N
.c. m ad N m et-e e P cs e O N N M ata e e P% c et. c.
- enno I'." " ' ! :. L"i "'
- 3/4 6 20 A-ent er. 'io. ". 6 (Change)
- J
gT Yj
~
I IABLE 3.6-1 (Cbntinued) v, E
o
,ki AUTOM /ITI C, inNIA]NMENT. ISOLATION VALVES u
VALVE NUMBER MAXIMUM E
C.
REAC10R BUILDING PURGE SUPPM ISOLATION TIME
, g AND EXilAUSl ISOLAl10N TUNCTION l.
0001A-All (SEC) lie.ictor iluilding Purge Suppiy 5
2.
00010-All I.ractor Building Purge Supply 5
3.
0002A-All 1:e.ictor Building Purge Exhaust 5
4.
00020-All 1:eactor Building Purge Exhaust 5
5.
6056-ilR -
6.
6057-IIR Alternate Reactor Building Purge Supply Line 5
Alternate Reactor Building Purge Supply Line 5
7.-
6066-ilR Alternate Reactor Building Purge Exhaust Line 5
8.
6067-IIR Alternate Reactor Building Purge Exhaust Line 5
D'.
MANU (I)
R 1.
8767-DN llemineralized Water Line N/A n
2.
8768-DN llemineralized Water Line N/A y
~3.
6772-FS Iire Service llose Reel Supply N/A g
4.
6773-FS
.Iire Service llose Reel Supply N/A 5.
2679-IA
=
lireathing Air Supply Line N/A 6.
2680-IA i athing Air Supply Line
.N/A-7.
6587-NG Supply To Steam Generators iN/A 8.
8090A-RC D"a
- it 4 Tester N/A 9.
80908-RC lbad We 1
ter N/A 10.
2912-SA Icactor Bui
~
ervice Air N/A 11.
6671-SF Refueling Cavi rain Line N/A J2.
6672-SF Refueling Cavity
'n Line 13.
6697-SF N/A
'~
liefueling Cavity Fill 3
~
e g
14.
6698-SF N/A I?nfueling Cavity Fill Line R
15.
7135-WL N/A Reactor Coolant Drain Tank Dis rge To Waste N/A E.
REMOTE MANUAL (2) g 1.
9602-CC 2.
8102A-CS Component Cooling To R. C. Pumps N/A 5
3.
81028-C5
!. cal Injection To Reactor Coolant Pump A N/A 4
8102C,CS
' cal Injection To Reactor Coolant Pump B N/A
!. cal Injection To Reactor Coolant Pump C N/A n
E
I TABLE 3.6-1 (Continued)
E 3
CONTAINMENT IS01.ATION VALVES E
MAXIMUM VALVE NUMBER ISOLATION TIME c.5 E. -REMOTE MANUAL ontinued)
FUNCTION (SEC)
-4
.5.
8107-CS Charging'Line To Regenerative Heat Exchange N/A g
6.
6050B-HR llydrogen Analyzer Return Line N/A 7.
6051A-HR llydrogen Analyzer Supply Line N/A 8.
60518-HR Hydrogen Analyzer Supply Line N/A 9.
6051C-HR liydrogen Analyzer Supply Line N/A 10.
6052A-HR lydrogen Analyzer Return Line N/A 11.
60528-HR I
ogen An lyzer Return Line N/A 12.
6053A-HR llydr en
'yzer Supply Line N/A l
13.
60538-HR llydroge n
y r Supply Line N/A 14.
8701A-RH RHR Pump From Reactor Coolant Loop A
'N/A 15.
87018-RH RHR Pump Suc n ro Reactor Coolant Loop C N/A 16.
8801A-SI Boran Injection n
Reactor Coolant loops N/A wh 17.
8801B-SI Boran Injection Ta To actor Coolant loops N/A 18.
8811A-SI RilR Pump A Suction Fr Re ~ culation Sump N/A m4
~
19.'
8811B-SI RHR Pump B Suction From rculation Sump N/A 20.
8884-SI High Head Safety Injection Reactor Coolant Loops N/A 21.
8885-SI liigh 11ead Safety Injection To actor Coolant Loops N/A 22.
8886-S1 High Head Safety Injection To Re tor Coolant Loops N/A' 23.
8888A-SI 1.ow flead Safety Injection To Reacto Coolant Loops N/A 24' 88888-SI Low Head Safety Injection To Reactor lant Loops N/A 25.
8889-51 Low Head Safety Injection To Re0ctor Coo t Loops N/A 26.
3003A-SP Supply To Reactor Building Spray Nozzles N/A 27.
30038-SP Supply To Reactor Building Spray Nozzles N/A 28.
3004A-SP Spray Pump A Suction From Recirculation Sump N/A 29.
3004B-SP Spray Pump B Suction From Recirculation Sump N/A 30.
3103A-SW Service Water From Reactor Building Cooling Unit A N/A 31.
31038-SW Service Water From Reactor Building Cooling Unit B
/A 32.
3106A-SW Service Water To Reactor Building Cooling Unit A N
33.
3106B-SW Service Water To Reactor Building Cooling Unit B N/A 34.
3110A-SW Service Water To Reactor Building Cooling Unit A N/A 35.
3110B-SW Service Water To Reactor Building Cooling Unit B N/A
._M
1 AllLE 3.6-1 (Continued) 5 CONIAlitMENT ISOLATION VALVES w
MAXIMUM i
c VALVE NUMBER ISOLATION TIME FUNCTION (SEC)
~
5 r.
CHECK u.
1.
7541-AC CRDM Coolant Water Inlet Line N/A 2.
7544-AC CROM Coolant Water Outlet Line N/A.
3.
9570-CC Component Cooling To R. C. Pump Bearings N/A 4.
9689-CC mponent Cooling From R. C. Pump Dearings N/A 5.
8103-CS Re< tor lant Pump Seal Water Return N/A 6.
8368A-CS Seal To R. C. Pump A N/A 7.
83688-CS Seal Inj n o R. C. Pump B N/A 8.
8368C-CS Seal Injec To C. Pump C N/A 9.
8381-CS Charging Line I g erative Heat Exchanger N/A 10.
6799-FS Fire Service Del o
arcoal Filters N/A 11.
2661-IA Instrument Air Supp o Reactor Building N/A w
12.
6588-NG Hitrogen Supply To Ste Generators N/A ls 13.
8046-RC Pressurizer Relief Tank cup Water Line N/A m
14 2913-SA Service Air Supply To Reacto Building N/A r5 15.
3009A-SP Supply To Reactor Building Spra Hozzles N/A R
16.
30098-SP Supply To Reactor Building Spray zies N/A 17.
8947-51 Accumlator Nitrogen Supply N/A 18.
8861-SI fill I.ine To Accumulators N/A W
Yb r ev w w
w wv y
w.
te O" O I^ #_
..^9
$ -'" CI I #_ "
5 3_ "O (9" MO P
'SU)
'[O $
11
"' *" ll' "0d by '""I"!StrCli" CO.9tTOl 1
'I'l"^ p '" I ' I "" ".
M, (2)
D05^t0 "2"U?
' n ^ -- net,pp!!:r51:
f--- 9.---Err 29, 1992, 27.til July 1, 193,"N (3)
The pre"!rica- - f c,-- ' f i - - t ' ^ "
y
,u, N