ML20154C989
| ML20154C989 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/06/1988 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20154C988 | List: |
| References | |
| NUDOCS 8805190010 | |
| Download: ML20154C989 (10) | |
Text
...
'Pog{ g,h{ _So,ng ( fa.nc b I
'88 Co<fanmack %or and Ega@rned a3d<M
- c o TABLE 3.6-1 (Continued) fl r.>
4 us hum o /t
~
88 $ (/
DD n 5
SECONDARY C0!4TAINMEllT BYPASS LEAKAGE PATHS on >
I PENETRATION TEST NUMBER SERVICE RELEASE LOCATION TYPE oo ty8$ :c '
M386 Containment Air Release Auxiliary Building Type C ZE ON" v1 O
M204 Containment Air Addition Auxiliary Building Type C g
e-M316 Int. Fire Protection Header -
Auxiliary Building Type C m
Hese Racks M337 Demineralized Water Auxiliary Building Type C M220 Instrume,t Air Auxiliary Building Type C M219 Station Air Auxiliary Building Type C R
M215 Breathing Air Auxiliary Building Type C T
M329 Reactor Coolant Pump Motor Oil Fill Auxiliary Building Type C M361 Int. Fire Protection Header -
Auxiliary Building Type C Sprinkleis M119 Containment Purge Exhaust Auxiliary Building Type C gB M331 Nitrogen Supply to Cold Leg Auxiliary Building Type C gg Accumulators M$
gg M322 Safety Injection Test Line Auxiliary Building Type C 1
zz oo M"5" U:lI Tcat Lira Auxiliary Building Type C Ltc 1 j
d M328N Component Cooling to Reactor Auxiliary Building Type C Vessel Support and RCP Coolers cc
. third *ad W#
hh g 7,
- Not applicable for Units),until after theh' refueling outag6 respeE
/*
f N,0 Net: 1.
"n
- ca;.,.'::3 ef,mtr:ti= 2;; ciate: uit' :!:' t!:r j ""I, thic geci'icatier is
^.y J
7
- 7' 5
't.
i
TABLE 3.6-2a (Continued)
UNIT 1 CONIAINMENT ISOLATION VALVES
>6 MAXIMUM c-VALVE NUMBER FUNCTION ISOLATION TIME (s)
-d 1.
Phase "A" Isolation (Continued)
KC-305B#
Excess Letdown Hx Supply Containment Isolation (Outside)
<20 e.
KC-315B#
Excess Letdown Hx Return Header Containment Isolation (Outside) 720 m
KC-320A#
NCDT Hx Supply Hdr Containment Isolation (Outside) 720 KC-332B#
NCOT Hx Return Hdr Containment Isolation (Inside) 720 KC-333A#
NCDT Hx Return Hdr Containment Isolation (Outside) 720 KC-429B RB Drain Heider Inside Containment Isolation 710 KC-430A RB Drain Header Outside Containment Isolation 310 NB-2608 Reactor Makeup Water Tank to Flush Header
<10 wk NC-53B Nitrogen to Pressurizer Relief Tank #1 Containment Isolation Outside
<10 m4 NC-54A Nitrogen to Pressurizer Relief Tank #1 Containment Isolation Inside 710 NC-56B RMW Pump Disch Cont Isolation 710 NC-1958 NC Pump Motor Oil Containment Isolation Outside 710
~
NC-196A NC Pump Motor Oil Containment Isolation Inside
{10 NF-228A Unit 1 Air Handling Units Glycol Supply Containment Isolation Outside
<10 NF-233B Unit 1 Air llandling Units Glycol Return Containment Isolation Inside 710 NF-234A Unit 1 Air Handling Units Glycol Return Containment Isolation Outside
{10 Supply Outside Containment Isolation
<10
- 'E NI-47A Accumulator N2 b
NI-95A Test Hdr Inside Containment Isolation 710 3%
NI-968 Test Hdr Outside Containment Isolation
<.10 NI-120B Safety Injection Pump to Accumulator Fill Lir.e Isolation 710 PP NI-122B#
Hot Leg Injection Check 1NI124, 1NI128 Test Isolation 710 zz NI-154B#
Hot Leg Recirculation Check 1NI125, 1NI129 Test Isolation 710 g
g fNI-2550 UMI Chcck Valve Test Linc helation 710' ff MI-250A UMI Chcck Valvc Test Linc helatica 710.Nute 1[
m %: 2000 L"l: Chcck Valwc Tcat Linc Outsidc Centair.rcat'Isolatica
]10j Note 1.
Upea capring of pcr.cications a;;;ciated with deletica......,...
- 'eci'icatic= 2rc ne k
iuasce apelichic.
[
m i
M5 Men'"
b*
g//.432%
li{ud ba*yk anel R, durn biof-
- a filo TABLE 3.6-2a (Continued) k UNIT 1 CONTAINMENT ISOLATION VALVES MAXIMUM VALVE NUMBER FUNCTION ISOLATION TIME (s) b 1.
Phase "A" Isolation (Continued)
(
^00 ^.
3;I CRck Vahe Test Line asit.c C;; tai. -:st Iseletica
- 10
",.e 1 g ;";;l-257^.
~
L"i! CMd "ch: T::t th: Incif C;at:5. r.t-he htica 710 i e.
NI-153M Hot Leg Injection Check NI156, MI159 Test Inlation 716 u
i NM-3A Pressurizer Liquid Sample Line Inside Containment Isolation
<10 NM-6A Pressurizer Steam Sample Line Inside Containment Isolation 210 NM-78 Pressurizer Sample Header Outside Containment Isolation 710 NM-22A E Hot Leg A Sample Line Inside Containment Isolation 210 M-25A NC Hot Leg C Sample Line Inside Containment Isolation 210 M-26B NC Hot Leg Sample Hdr Outside Containment Isolation 210
)
NM-728 NI Accumulator 1A Sample Line Inside Containment Isolation 710 w
NM-758 NI Accumulator 18 Sample Line Inside Contairment Isolation 710 m4 NM-788 NI Accumulator IC Sample Line Inside Containment Isolation 210 M-818 NI Accumulator ID Sample Line Inside Containment Isolation 710 M-82A NI Accumulator Sample Hdr Outside Contairment Isolation 7)n NM-187M SG 1A Upper Shell Sasple Containment Isolation Inside 710 M-190M SG 1A Blowdown Line Sample Containment Isolation Inside 210 MM-191M SG 1A Sample Hdr Containment Isolation Outside 710 NM-197M SG 1B Upper Shell Sample Containment Isolation Inside 710 N>i-200 M SG 1B Blowdown Line Sample Containment Isolation Inside 710 kk M-201M SG 18 Sample Hdr Containment Isolation Gutside 710 M-207M SG IC Upper Shell Sample Containment Isolation Inside 710 kk NM-210M SG IC Blowdown Line Sample Containment Isolation Inside 210 ga NM-211M SG IC Sample Hdr Containment Isolation Outside 510 NM-217M SG 1D Upper Shell Sample Containment Isolation Inside
<10
??
NM-220M SG 10 Blowdown Line Sample Containment Isolation Inside 210 2z M-221M SG 1D Sample Hdr Containment Isolation Outside 310
??
NV-158 Letdown Containment Isolation Outside
$10 NV-89A NC Pumps Seal Return Containment Isolation Inside
$10 NV-918 NC Pumps Seal Return Containment Isolation Outside
$10 NV-314M Charging Line Containment Isolation Outside
$10 ug
$i55_ '5.__If[
=
(,
....r.
TABLE 3.6-2a (Continued) 9y UNIT 1 CONTAINMENT ISOLATION VALVES ai 2
MAXIMUM VALVE NUMBER FUNCTION ISOLATION TIME (s) 3.
Manual (Continued) e SM-103#
Main Steam IC N.A.
^2 SM-Il9#
Main Steam IC N.A.
SM-141#
Main Steam IC N.A.
SA-4#
Main Steam IC N.A.
SM-19#
Main Steam ID N.A.
SM-70#*
Main Steam 10 N.A.
SM-102#
Main Steam 10 N.A.
SM-118#
Main Steam 10 N.A.
SM-140#
Main Steam ID N.A.
m}
WE-20*
Cont Bldg Supply 1901 N.A.
WE-22*
Cont Bldg Supply Isol N.A.
g, WE-56*
Cont Bldg Supply Isol N. A.-
e FW-4*
Refueling Water N.A.
NV-862#*
Pressurizer Auxiliary Spray ND Dutside Containment N.A.
WLA-21#*
Steam Generator Drain Pump Discharge Outside Containment Isolation N.A.
WLA-24#*
Steam Generator Drain Pump Discharge Outside Containment Isolation N.A.
TABLE NOTATIONS
- May be opened os.... :ntermittent basis under administrative control.
- Valve also receives a igh Radiation (H) and/or a High Relative Humidity isolation signal.
- No, subject to Type C leakage tests.
NOTE:
Times are for valve operation only, and do not include any sensor response or circuit delay times.
See Specification 3/4 3.2 for system actuation response times.
- kN A{ch applia0t. hrl$ni$ $ un N ahec & hird n&elshf ekaye,
TABLE 3.6-2b (Continued)
UNIT 2 CONTAINMENT ISOLATION VALVES
>5 MAXIMUM e
c VALVE NUMBER FUNCTION ISOLATION TIME (s) 5U 1.
Phase "A" Isolption (Continued) e p.
KC-3058#
Excess Letdown Hx Supply Containment Isolation (Outside)
<20 to KC-315B#
Excess Letdown Hx Return Header Containment Isolation (Outside) 220 KC-320A#
NCDT Hx Supply Hdr Containment Isolation (Outside) 220 l
KC-3328#
NCDT Hx Return Hdr Containment Isolation (Inside) 220 KC-333A#
NCOT Hx Return Hdr Containment Isolation (Outside) 720 KC-429B RB Drain Header Inside Containment Isolation 710 KC-430A RB Drain Header Outside Containment Isolation 510 w
NB-2608 Reactor Makeup Water Tank to Flush Header
<10
~u m
NC-53B Nitrogen to Pressurizer Relief Tank #1 Containment Isolation Outside
<10 de NC-54A Nitrogen to Pressurizer Relief Tank #1 Containment Isolation Inside 710 NC-568 RMW Pump Disch Cont Isolation 210 NC-195B NC Pump Motor Oil Containment Isolation Outside 710 NC-196A NC Pump Motor Oil Containment Isolation Inside 310 NF-228A Unit 2 Air Handling Units Glycol Supply Containment Isolation Outside
<10 NF-2338 Unit 2 Air Handling Units Glycol Return Containment Isolation Inside 710 NF-234A Unit 2 Air Handling Units Glycol Return Containment Isolation Outside
{10 N&
NI-47A Accumulator N Supply Outside Containment Isolation
<10 2
NI-95A Test Hdr Inside Containment Isolation 710 NI-968 Test Hdr Outside Containment Isolation 710 NI-1208 Safety Injection Pump to Accumulator Fill Line Isolation E10 NI-122B#
Hot Leg Injection Check 2NI124, 2NI128 Test Isolation 710 g
NI-154B#
Hot Leg Recirculation Check 2NI125, 2NI123 Test Isolation E10 9:I=
I Cr=x va:= T=t u= neuu
w ck
""! Ch::k !al a T= t Li= h;lati n 110 hte 1 EE fMI-250^
22 el2cce
I Cr=x nix T=t u= e;uie; eauf z.=.e umuu=
ge, 1
/
ro U OC cCppiOg Of PCCCtTCtiGGL EssOCiCtCd b"!tI dClCIiOG O[ N!,1hCO CEOCifiCCt!G..1 GTC T.G btC 1.
F 4) ung:T cpp?icet?c.
- d-436A U g d l L pl2 L ei O rn 6 Ou b de b r e al I5o U on M
W TABLE 3.6-2b (Continued) l 9
UNIT 2 CONTAINMENT ISOLATION VALVES
-i MAXIMUM VALVE NUMBER FUNCTION ISOLATION TIME (s) x 1.
Phase "A" Isolation (Continued) r "I 20C".
E! Chc k V;'.. T ;t Linc In;id: C;ntai. x nt h ;!:ti -
110'
";t; 1 e-JI 2G7,",
U"I C kck Valvc Test Linc Insid: Centa!.nnt Eclatica
?10 s
N NI-153M Hot Leg Injection Check NI156, NI159 Test Isolation ild NM-3A Pressurizer Liquid Sample Line Inside Containment Isolation
<10 NM-6A Pressurizer Steam Sample Line Inside Containment Isolation 710 NM-78 Pressurizer Sample Header Outside Containment Isolation 710 NM-22A NC Hot Leg A Sample Line Inside Containment Isolation E10 NM-25A NC Hot Leg C Sample Line Inside Containment Isolation 210 R
NM-26B NC Hot Leg Sample Hdr Outside Containment Isolation 710 4-HM-728 NI Accumulator 2A Sample Line Inside Containment Isolation 210
?
NM-75B NI Accumulator 28 Sample Line Inside Containment Isolation E10 g
NM-788 NI Accumulator 2C Sample Line Inside Containment Isolation 210 NM-818 NI Accumulator 20 Sample Line Inside Containment Isolation 710 NM-82A NI Accumulator Sample Hdr Outside Containment Isolation 210 NM-187M SG 2A Upper Shell Sample Containment Isolation Inside 210 NM-190M SG 2A Blowdown Line Sample Containment Isolation Inside 710 NM-1918#
SG 2A Sample Hdr Containment Isolation Outside 710 NM-1978#
SG 28 Upper Shell Sample Containment Isolation Inside 710 NM-200B#
SG 28 Blowdown Line Sample Containment Isolation Inside 710
[k NM-201M SG 28 Sample Hdr Containment Isolation Outside 210 mo NM-207M SG 2C Upper Shell Sample Containment Isolation Inside E10 (k
NM-210M SG 2C Blowdown Line Sample Containment Isolation Inside 710 NM-2118#
SG 2C Sample Hdr Containment Isolation Outside 210 as NM-2178#
SG 2D Upper Shell Sample Containment Isolation Inside 710
((
NM-220B#
SG 2D Blowdown Line Sample Containment Isolation Inside 310 NM-221M 5G 2D Sample Hdr Containment Isolation Outside
<10 EE NV-ISB Letdown Co'ntainment Isolation Outside
<10
$7 NV-89A NC Pumps Seal Return Containment Isolation Inside 710 N-NV-918 NC Pumps Seal Return Containment Isolation Outside 710 NV-314B#
Charging Line Containment Isolation Outside 310
~
"st: 1:
"pan ::ppin;; cf penciratica; ;;;cc!;ted with d-1 tien of U"I, there speci'icati:n; cre n; 7
i.._._.u._.._... a.,y.. m...
TABLE 3.6-2b (Continued) 9 l
g UNIT 2 CONTAINMENT ISOLATION VALVES 2-MAXIMUM g
VALVE NUMBER FUNCTION ISOLATION TIME (5)
'a 3.
Manual (Continued) 9-SH-103#
Main Steam 2C N.A.
N SM-119#
Main Steam 2C N.A.
SM-141#
Main Steam 2C N.A.
SA-4#
Main Steam 2C N.A.
SM-19#
Main Steam 2D N.A.
SM-70#*
Main Steam 20 N.A.
SM-102#
Main Steam 2D N.A.
SM-115#
Main Steam 20 N.A.
i SM-140#
Main Steam 2D N.A.
}
{
WC-20*
Cont Bldg Supply Isol N.A.
WE-22*
Cont Bldg Supply Isol N.A.
i 3
WE-56*
Cont B1dg Supply Isol N.A.
u FW-4*
Refueling Water N.A.
l NV-d62#*
Pressurizer Auxiliary Spray ND Outside Containment N.A.
WLA-21#*
Steam Generator Drain Pump Discharge Outside Containment Isolation N.A.
WLA-24#*
Steam Generator Drain Pump Discharge Outside Containment Isolation N.A.
i 1
TABLE NOTATIONS 1
f
- May be opened on an intermittent basis under administrative control.
- Valve also receives a liigh Radiation (II) and/or a liigh Relative Humidity isolation signal.
4
- Not subject to Type C leakage tests.
NOTE:
Times are for valve operation only, and do not include any sensor response or circuit delay times.
See Specification 3/4 3.2 for system actuation response times.
m a # mc,asz_u a a m. u g 4
t Discussion and No Significsnt Hazards Analysis a
t I
l l
e i
I r
i i
1 e
i l
)
i
?
r i
3 4
?
DISCUSSION AND NO SICNIFICANT llAZARDS ANALYSIS The proposed amendment would:
(1) Add penetration M-375 to Table 3.6-1; (2) Add valve NM-438B to Tables 3.6-2a and 3.6-2b; and (3) Delete information which is no longer applicable.
The additions to the Tables will be required due to the scheduled implementation of a station modification which will reroute a Post Accident Liquid Sample (PALS) drain line in each unit.
The PALS equipment is a part of the Nuclear Sampling (NM) System at Catawba which has been designed in accordance with the recommendations contained in NUREG-0737, item II.B.3.
The modification to the NM System will involve removing the discharge line from the PALS panel which is currently routed to the Waste l
Evaporator Feed Tank Sump.
A new line consisting of 0.5" stainless steel fobing will route discharge from the PALS panel to the Containment Floor and Equipchnt sump. A new Containment penetration (M-375) will be required since the new line will go through the Nuclear Sample Lab wall, Reactor Building and Containment wall. Class B Containment isolation valves (NM-438B) will be installed te maintain Containment integrity.
Rerouting of the drain line will ensure that any residual samples collected from the PALS panel will be returned to the Containment. This is consistent with the guidance contained in NUREG-0737.
This modification is scheduled to be implemented during the next refueling outages for each Unit.
The third refueling outage for Unit 1 is currently scheduled to begin on December 14, 1988 and finished on February 8,1989. The Unit 2 second refueling outage is currently scheduled to begin on February 9, 1989 and end on April 10, 1989. The proposed wording for the Technical Specification changes have been conditioned such that the changes may be issued prior to these outages but not be applicable until after the modifications have been installed.
The proposed Technical Specification amendment would also delete some wording from each of the affected Tables which is no longer applicable. As such, this portion of the amendment request is strictly administrative.
10 CFR 50.92 states that a proposed amendment involves no significant hazards considerations if operation in accordance with the proposed amendment would nots (1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety.
The proposed changes do not involve a significant increase in the probability or j
consequences of an accident previously evaluated. The amendment would add a l
penetration and several valves to Tables contained within the Specification. The additions are the result of the rerouting of the PALS drain line back into Containment. The rerouting is to be done in accordance with the guidance
DISCUSSION AND NO SIGNIFICANT IIAZARDS ANALYSIS (Continued) l contained in NUREG-0737, item II.B.3. to reduce radiation exposure from reactor coolant samples. The amendment would also make several administrative changes to the Tables.
This amendment will therefore not effect the probability of any accidents and will reduce the consequences in terms of reduction in personnel dose.
The proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated. The modification involves a change to the post-accident liquid sampling panel.
The administrative changes will have no effect on the operation of the station. Therefore, no new modes of reactor operation are introduced and the design of the Reactor Coolant System and its primary support systems are not affected.
The proposed changes will not result in a significant reduction in a margin of safety. The rerouting of this drain line will not introduce any new possible failure modes. There is no potential leakage outside containment because of the installation of the qualified containment isolation valves and the design of the penetration. Overall, the potential for radiation exposure will be reduced. The administrative changes will not effect any margin of safety.
Based on the above discussion, Duke Power concludes that this proposed amendment does not involve Significant Hazards Considerations.
.