ML20203D480
| ML20203D480 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 07/14/1986 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20203D477 | List: |
| References | |
| NUDOCS 8607210225 | |
| Download: ML20203D480 (7) | |
Text
. _ _
B %.6-l TABLE M (Continued)
SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS A
TEST PENETRATION NUISER SERVICE RELEASE LOCATION TYPE Cont. Press. Monitor -
Auxiliary Building Type C 3
Narrow Range g
k M354 Fuel Transfer Tube Auxiliary Building Type B m
4 l
^
R T
O If ao kk a
55 E F.
22 i
oa p ener caricn is The UH I rest lint and w. tJ be foe
?ALS disthog c foIlewig 33 ec
- tk T his implementanon o f N Sm I-1761, I-I?68, 2 -s93, cod 2 -598 t he.
I 8607210225 860714 DR ADOCK 05000369 POR
5 Jh. G '
TABLF M E
CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION E
VALVE NUMBER FUNCTION TIME (SEC) i Z
t 1.
Phase "A" Isolation l
~
88-18#
Steam Generator A Blowdown Containment Outside Isolation
<10 B8-2B#
Steam Generator B Blowdown Containment Outside Isolation 710 88-38#
Steam Generator C Blowdown Containment Outside Isolation 710 BB-4B#
Steam Generator D Blowdown Containment Outside Isolation 710 BB-5A#
Steam Generator A Blowdown Containment Inside Isolation 710 BB-6A#
Steam Generator B Blowdown Containment Inside Isolation 710 BB-7A#
Steam Generator C Blowdown Containment Inside Isolation 710 i
en BB-8A#
Steam Generator D Blowdown Containment Inside Isolation
{l0 t'
CF-26AB#
Steam Generator D Feedwater Containment Isolation
<5 CF-28AB#
Steam Generator C Feedwater Containment Isolation 75 T
CF-30AB#
Steam Generator B Feedwater Containment Isolation 75 l
T CF-35AB#
Steam Generator A Feedwater Containment Isolation 75 T
$O CF-1268 Steam Generator A Main Feedwater to Auxiliary Feedwater Nozzle Isolation CF-127B Steam Generator B Main Feedwater to Auxiliary Feedwater 110 Nozzle Isolation CF-1288 Steam Generator C Main Feedwater to Auxiliary Feedwater 110 FF Nozzle Isolation
$ 'd CF-1298 Steam Generator 0 Main Feedwater to Auxiliary Feedwater 110 if Nozzle Isolation
&[J Steam Generator A Feedwater Containment Isolation Bypass
<10 3
CF-134A CF-135XS Steam Generator B Feedwater Containment Isolation Bypass 710 l
l By CF-136A Steam Generator C Feedwater Containment Isolation Bypass 510 CF-137A Steam Generator D Feedwater Containment Isolation Bypass
<10 J
CF-15168 Auxiliary Nozzle Temper SG A 510 EE hh ec
~ !
I l
s 3/y.t; l TABLE M (Continued) '
CONTAllelENT ISOLATION VALVES
{,
o j
E MAXIIt#1 ISOLATION FullCTION TIME (SEC) h VALVE leBSER 4
1.
Phase "A" Isolation (continued) g
<10 k
CF-153A Aux 111ery llozzle Temper SG B 710 i
CF-1558 Aux 111ary llezzle Temper SG C i
CF-1578 Auxiliary flozzle Temper SG 0 310 1
Excess Letdoun Hu Supply Pent. Isolation Outside
<30 i
KC-30508 Excess Letdoun Nx Ret. Ndr. Pent. Isolation Outside 730 1
E-31588 715 l
E-3204 IICOT Hu Supply Ndr. Pent. Isolation Outside 715 E-3328 IICOT lix Supply Ndr. Pent. Isolation Inside e,.
IICOT Hu Return Ndr. Pent. Isolation Outside 715 i
l E-3334 RS Drain Header Inside Containment Isolation 715
)
E-4298 RB Drain Header Outside Containment Isolation 315 E-4304 I
18-2600 Reactor Blakeup Water Tank to NW System 115 c
<10 NC-538 Nitrogen to Pressurizer Relief Tank Containment
}
Isolation Outside
<10 IIC-54A Nitrogen to Pressurizer Relief Tank Containment Isolation Inside 1
<10 1
IIC-568 PRT Makeup IIS l
IIC-1958 MC Pump Motor Oil Containment Isolation Outsiglo l
11C-196A IIC Pump Motor 011 Containment Isolation Inside 515 l
NF-228A Air Handling Units Glycol Supply Containment
$15 l
Isolation Outside i
I 11F-233g6 Air Handling Units Glycol Supply Containment 115 Isolation Inside 11F-234A Air Handling Units Glycol Supply Containment 115 Isolation outside 2
Accumulator Nitrogen Supply Outside Containment
$15 MI-47A Isolation i
MI-954 Test HDR Inside Containment Isolation
$10 1
B 3h.G-L l
TABLE 3 E=3-(Continued)
/
I CONTAllelENT ISOLATI001 VALVES
.I.
ISOLATION l
FUIICTION TIIE (SEC) j e
g VALVE NLeSES 1
Q j
M 1.
Phase "A" Isolation (continued)
=
NI-968 Test HDB Outside Containment Isolation
<10 i
w Safety Injection Pump to Accumulator Fill Line Isolation 710 l
E.
NI-1208 Hot Leg Injection Check NI124, NI128 Test Isolation 710
(
w NI-12 i
NI-2558 Note 1 UNI Check Valve Test Line Isolation 210 i
NI-258A[
UNI Check Valve Test Line Isolation 710 UHI Check Valve Test Line Isolation 710 NI-2648 p UNI Check Valve Test Line Isolation 710 i
NI-266A NI-267AJ UHI Check Valve Test Line Isolation
{10 m
Pressurizer Liquid Sample Line Inside Containment Isolation
<15 l
R let-3AC.
Pressurizer Steam Sample Line Inside Containment Isolation 715 let-6A Pressurizer Sample Header Outside Containment Isolation 715 T
300- 7 8 NC Hot Leg #1 Sample Line Inside Containment Isolation 715 a
i E
let-22AC I
IIC Hot Leg M Sample Line Inside Containment Isolation EIS l
.r let-25AC.
NC Not Legs Sample Ndr. Outside Containment Isolation 715 1
100-268 NI Accumulator A Sample Line Inside Containment Isolation 715 100-728 l.
NI Accumulator 8 Sample Line Inside Containment Isolation 715 100-758 j
NI Accumulator C Sample Line Inside Containment Isolation 715 100-788 NI Accumulator 0 Sample Line Inside Containment Isolation 715 400-818 NI Accumulator Sample Ndr. Outside Containment Isolation 715
((
let-82A let-187Af SG A Upper Shell Sample Containment Isolation Inside 715 SG A Blowdown Line Sample Containment Isolat. ion Inside 715 ga g[
let-190M 715 let-1918f SG A Sample Ndr. Containment Isolation Outside 715 let-1978f SG B Upper Shell Sample Containment Isolation Inside
=3 SG B Blowdoun Line Sample Containment Isolation Inside 715 II let-2008f 715 let-201Ad SG.8 Sample Ndr. Containment Isolation Inside 715 let-207Af SG C L W r Shell Sample Containment Isolation Inside SG C Blowdown Line Sample Containment Isolation Inside 715 naEE let-210M 715
%E let-2118f SG C Sample Ndr. Containment Isolation Outside 715 let-2178f SG D Upper Shell Sample Containment Isolation Inside SG D' Blowdown Line Sample Containment Isolation Inside 315 mw let-22088 Upon the deactivation of the UHI Syst ~ by removal of related components and piping Note 1:
and modifications to the Cold Leg Aci lators, this specification is no longer applicab'
i B 5/q.fo - 2_
TABLE W (Continued)
.?
CONTAlleqENT ISOLATION VALVES
- n I$
MAXItt24 JA ISOLATION TIME (SEC) lc FUNCTION
! j5 VALVE NUISER 1.
Phase "A" Isolation (continued) i SG D Sample Hdr. Containment Isolation outside
$15 lk let-221A#
<10 Letdown Containment Isolation Outside 210
. na l
NV-78#
NC Pumps Seal Return Containment Isolation Inside 210 NV-94M NC Pumps Seal Return Containment Isolation Outside 5
11 NV-958#
45 gpa Letdown Orifice Outlet - Containment Isolation (15 NV-457M 75 gpa Letdown Orifice Outlet - Containment Isolation 215 NV-458M High Pressurizer Letdown Orifice Outlet - Containment f
NV-459M Isolation
<15 Standby Makeup Pump Suction Containment Isolation Inside 215 l
NV-842AC Standby Makeup Pump to RCS seals
~
NV-849AC l
w
<15 l k Containment Isolation Outside (Unit 1)
RF-821A Containment Isolation Outside (Unit 2)
$15 RF-832A l g
$15 Breathing Air Containment Isolation
,d V8-498
<15 Containment #2 Purge to Annulus Inside Containment Isolation 715 i
VE-SA Containment #2 Purge to Annulus Outside Containment Isolation EIS i
VE-68 Containment #2 Purge Blower Outlet, Containment Isolation l
VE-10A (outside)
Instru. Air Upper Containment Outside Isolation
$15 VI-1488 J
l l
l i
n
l l
ATTACHMENT 2 i
i.
j SUMARY OF CHANGES AND JUSTIFICATION This proposal supplements a May 14, 1986 submittal and makes changes to that 4
submittal. The May 14 submittal sought to move two tables (listing secondary i
containment bypass leakage paths and containment isolation valves) from the i
Technical Specifications to the bases and to add three penetrations and update the tables for other planned modifications.
Subsequent discussions have concluded that it is not necessary to add the three penetrations (Outage service penetrations) to the table. This conclusion was reached as these penetrations terminate in the annulus and thus any leakage would exhaust through the annulus ventilation system.
The annulus ventilation system is described in FSAR section 6.2.3 for operation and filters which would minimize any j
actual radioactive leakage through the service penetrations. This portion of the May 14 proposal is thus withdrawn.
l The other changes to the table are the result of an internal audit which determined that several valve designations in Table 3.6-2 (proposed B 3/4.6-2, Containment Isolation Valves) were incorrect. These are summarized below:
Change CF-151A to CF-151B
,l CF-135A to CF-135B NF-233A to NF-233B NM-25A to NM-25AC NV-849A to NV-849AC NM-3A to NM-3AC NM-22A to NM-22AC b
The changes in valve train designations are strictly administrative in nature and j
do not impact plant safety or operation.
1 5
1 l
i
)
i a
J t
i l
i 1
l
i i
ATTACHMENT 3 I
ANALYSIS OF SIGNIFICANT HAZARDS CONSIDERATIONS As required by 10CFR 50.91, this analysis provides a determination that the proposed changes to the Technical Specifications do not involve any significant hazards considerations, as defined by 10CFR 50.92.
i The deletion of the service penetrations from the table requires no significant hazards considerations analysis as this action is simply withdrawing a portion of an earlier, not yet approved, proposal.
Operation in accordance with the proposed change would not involve a significant j
increase in the probability or consequences of an accident previously evaluated.
j The change in valve designations is an administrative matter that causes no j
operational changes were made to the valves; this fact leads to the conclusion
'l that no accident scenarios are affected - in terms of probability or consequences, j
Operation in accordance with the proposed change would not create the possibility of a new or different kind of accident from any accident previously evaluated.
The changes in valve designation are an administrative matter which do not involve any hardware modifications or operational changes.
In the absence of such a change, no new possible accident sequences or scenarios are created.
Operation in accordance with the proposed change would not involve a significant reduction in a margin of safety. The changes in valve designatione are administrative in nature and do not impact plant operations or any operational margins.
4 f
Based upon the preceding analyses, Duke Power Company concludes that the proposed j
changes to the McGuire Nuclear Station Technical Specifications do not involve any l
significant hazards considerations.
j i
i 1
1 J
i