ML19332C963
| ML19332C963 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/20/1989 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML19332C962 | List: |
| References | |
| NUDOCS 8911290236 | |
| Download: ML19332C963 (7) | |
Text
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' to Document C:ntrol Desk Letter'
-4 November 20, 1989 Page 1 of 3 i
A1TACHMENT 1 1
i Technical Specification Pages with Changes indicated h
Specification Chance Description j
3/4358 3/4.3.3.6, Table 3.3 10 Delete item 14 and rename item 13 l
" Reactor Building /RHR Sump Level" e
3/4 3-60 3/4.3.3.6, Table 4.3 7 Delete item 14 and rename item 13
" Reactor.Bullding/RHR Sump Level" i
I k
t 8911290236 891120 PDR ADOCK 05000395 P
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g TABLE 3.3-10 (Continued)
%g-on 7
E
- s woe ACC10ENT fGNITORING INSTRIMENTATION e
E M;0 o
TOTAL MINIptpl 8
INSTRUMENT 0F CHANNELS pp CHANNELS OPERA 8tE g
g 13 Reactor Bufidi Sump Level 2
1
^
orwrt E
q o
15.
Condensate Storage Tank Level 2
1
?
16.
Reactor Building Cooling Unit Service Water Flow E-
^
-2 1
E 17.
Service Water Temperature-Reactor Building Cooling Unit 2 pairs 1 pair
{
(Inlet and Discharge) k, Y
18.
NaOH Storage Tank Level i
E 2
1 i
19.
Reactor Coolant System Subcooling Margin Monitor i
i 2
1 20.
Pressurizer PORY Position Indicator 2/ valve
- 1/ valve
- 21.
Pressurizer PORY Block Valve Position Indicator 4
1/ valve 1/ valve i
22.
Pressurizer Safety Valve Position Indicator 2/ valve 1/ valve 23.
In-Core Thermocouples 4/ core 2/ core quadrant quadrant -
l 24.
Reactor Vessel level 2
1 Mot required when the associated block valve is closed per Specification 3.4.4.
l
'r 255 e<r.
eea w&E g
TABLE 4.3-7 (continued) a3 o
"mg_
- =
ACCIDENT penITORING IstSTmSENTATION SURVEILLANCE REQUIREfENTS wp_
e
.eo e3 CHAfu1EL CHAfuEL -
- o INSTRLNENT DECK CALISMTION h
1
- w
=
1 5
4 12.
Reactor 8u11 ding Temperature M
a 3
h; 13.
Reactor Buildi Samp level M
R I
OftfrE 8
n ym M,_,,,, 7 f o
i i
15.
Condensate Storage Tank Level M
R i
l 16.
Reactor Building Cooling Unit Service M
R g
Water Flow p
w e
N 3
17.
Service Water Temperature - Reactor Building M
R Y
Cooling Unit (Inlet and Discharge)
.i e
o 18.
NaOH Storage Tank Level M
R i
j 19.
Reactor Coolant System Subcooling Mergin Monitor M
R 20.
Pressurizer PORY Position Indicator M*
R*
i i
21.
Pressurizer PORY 81ock Valve Position Indicator M
R f
22.
Pressurizer Safety Valve Position Indicator M
R i
i 23.
In-Core Therreocouples.
M R
24.
Reactor Vessel Level M
R j
i i
ANot required when the associated block valve is closed per Specification 3.4.4.
-i
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_ _. _..., _..., _ _ _.... _.., ~. -
.4
- 13 Docum:nt Contr:l Desk Lett:r N;vember 20,1989
. Page 1 of 2 t
.t ATTACHMENT 2 i
i Description of Amendment Request l
Safety Evaluation I
l-l-
I, 1 tJ Document Contr;l Desk L0tt:r i
November 20,1989
.Page 2 of 2 SAFETY EVALVATION FOR VIRGIL C. SUMMER NUCLEAR STATION Description of amendment request:
Technical Specification 3/4.3.3.6. " Accident Monitoring Instruments."
presently requires two channels of Reactor Building RHR Sump Level (Item 13
'r in Table 3.3-10 and 4.3-7) and two channels of Reactor Building Level (Item-14 in Tables 3.3-10 and 4.3-7).
SCELG requests a deletion of " Reactor o
Building Level" from the tables and modification of the " Reactor Building RHR Sump Level" to read " Reactor Building /RHR Sump Level."
The Technical Specifications bases for accident monitoring instruments are to provide sufficient information from selected parameters to monitor and assess these variables following an accident and to remain consistent with recommendations of Regulatory Guide 1.97.
The proposed change in Technical Specifications is requested as part of a planned modification. This modification integrates the Reactor Building RHR Level Instrument and the Reactor Building Level Instrument into a new single instrument. This will be done for each channel.
The new instrument provides indication over the range previously provided by the combination of both of the old instruments. The modification accomplishes two positive benefits. One being the removal of a piece of equipment from inside containment without removing its function. The other benefit is the new instrument is less susceptible to environmental hazards.
Safety Evaluation:
P The Technical Specification bases for accident monitoring instruments are still complied with upon making this modification. This modification does not change the capability of monitoring the Reactor Build %g level during accident conditions. The determination of NPSH requirements for RHR during swapover to the sumps, along with the ability to monitor reactor building level for consideration of non-safety related equipment protection, still exists. The requirements as prescribed by Regulatory Guide 1.97 are met and the modification improves the environmental qualification of the instrument.
This modification makes the function of the instrument (indication only) more reliable and more accurate. This results in enhanced operator information that is used to monitor and assess plant conditions during an accident, i
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', 13 Docum2nt Ccntr;l Desk LGtt2r i
i
,.~
N';vember 20,1989 i
Page 1 of 2 i
1-n i
ATTACHMENT 3 i
w Description of Amendment Request l
No Significant Hazards Evaluation t-i i
i l
l I
t 0
f t
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l l
. -... _. -. -, ~ _.
e. 13 Document Ccntrd Desk Lctt:r l
November 20,1989 L
Page 2 of 2 Description of amendment request; Technical Specification 3/4.3.3.6. " Accident Monitoring Instruments."
presently requires two channels of Reactor Building RHR Sump Level (Item 13 in Table 3.3-10 and 4.3-7) and two channels of Reactor Building Level (Item 14 in Tables 3.3-10 and 4.3-7).
SCE&G requests a deletion of " Reactor Building Level" from the tables and modification of the " Reactor Building RHR Sump Level" to read " Reactor Building /RHR Sump Level."
The Technical Specifications bases for accident monitoring instruments are to provide sufficient information from selected parameters to monitor and assess these variables following an accident and to remain consistent with recomrt;ndations of Regulatory Guide 1.97.
The proposed change in Technical Specifications is requested as part of a planned modification. This modification integrates the Reactor Building RHR Level Instrument and the Reactor Building Level Instrument into a new single instrument. This will be done for each channel.
The new instrument provides indication over the range previously provided by the combinaticn of both of the old instruments. The modification accomplishes two positive benefits. One being the removal of a piece of equipment from inside containment without removing its function. The other benefit is the new instrument is less susceptible to environmental hazards.
No Significant Hazards Evaluation:
Upon review of the proposed amendment, it has been determined that no significant hazard considerations exist for the following reasons:
1.
The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated since the information available from accident monitoring instruments has not changed and the affected instruments are " indication only" instruments.
2.
The proposed ~ change does not create the possibility of a new or different kind of accident from any evaluated previously because the change involves passive components only.
3.
The proposed change does not involve a significant reduction in the margin of safety due to the fact that the modification results in a more reliable and accurate indication of the selected parameters.
Therefore, based on the above considerations. SCE&G has determined that this change does not involve a significant hazards consideration.