ML20116P340
| ML20116P340 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/30/1985 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20116P341 | List: |
| References | |
| NUDOCS 8505080007 | |
| Download: ML20116P340 (8) | |
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q UNITED STATES
[
y, NUCLEAR REGULATORY COMMISSION
' 11 j
WASHINGTON, D. C. 20655
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n SOUTH CAROLINA ELECTRIC & GAS COMPANY
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SOUTH CAROLINA PUBLIC SERVICE AUTHORITY q
DOCKET NO. 50-395 b
VIRGIL C. SUMER NUCLEAR STATION, UNIT NO. I
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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 h
License No. NPF-12 1
[
1.
The Nuclear Regulatory Commission (the Comission) has found that:
U A.
The application for amendment to the Virgil C. Sumer Nuclear Station, Unit No. 1 (the facility) Facility Operating License No. NPF-12 filed i
by the South Carolina Electric & Gas Company acting for itself and p
South Carolina Public Service Authority (the licensees), dated August 24, 1984, and revised November 14, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as
(
amended (the Act)-and the Commission's regulations as set forth in l.0.,CFR Chapter I,;
B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance:
(i) that the activities authorized by this' amendment can be conducted without endangering the health and.
safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR J
Chapter I; 5
D.
The issuance of this license amendment will not be inimical to the j
comon defense and security or to the health and safety of the public; n
i E.
The issuance of this license amendment is in accordance with 10 CFR
'i Part 51 of the Commission's regulations and all applicable require-b ments have been satisfied.
2.
Accordingly, the license is hereby amended by page changes = to the Technical q"
Specifications as indicated in the attachments to this license amendment and paragraph 2.C(2) of Facility Operating License No. NPF-12 is hereby amended j;
to read as follows:
(2) Technical Specifications y
The Technical Specifications contained in Appendix A, as revised 4
through Amendment No. 40 are hereby incorporated into this license.
F South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental m
Protection Plan.-
l 8505080007 850430
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This license amendment is effective seven days after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l& h
/W Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Enclosure:
Technical Specification Changes Date of Issuance: April 30, 1985 g
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i ATTACHMENT TO LICENSE AMENDMENT NO. 40 1
FACILITY OPERATING LICENSE NO. NPF-12 3
DOCKET NO. 50-395 k
4 i
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and i;
contain vertical lines indicating the areas of change. Corresponding overleaf pages are also provided to maintain document completeness.
Amended Overleaf Pages Pages 2-6 2-5 2-8 3/4 3-28 3/4 3-27 t
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. ht TABLE 2.2-1 h
'{h E
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS
- jf.
Mi Total
'he
{
Functional Unit Allowance (TA)
Z_
S, Trip Setpoint
' Allowable Value c
s 1.
Manual Reactor Trip Not Applicable NA NA NA NA' f
i
/
2.
Power Range, Neutron Flux 7.5
'4.56 0
1109% of RTP
$111.2% of RTP High Setpoint 4
Low Setpoint 8.3
,4.56 0
.5 0
$5% of RTP with 16.3% of RTP with l
0 3.
Power Range, Neutron Flux 1.6 High Positive Rate a time constant a time constant 12 seconds
>2 seconds 4.
Power Range, Neutron Flux 1.6 0.5 0
<5% of RTP with
<6.3% of RTP with 4
High Negative Rate a time constant a time constant a
di
>2 seconds
>2 seconds b
l S.
Intermediate Range, 17.0 8.4 0
Neutron Flux i
6.
Source Range, Neutron Flux 17.0 10.0 0
$105 cps
$1.4 x 105 cps i.
r7, 7.
Overtemperature AT 7.1 2.94 1.8 See note 1 See note 2
[h-t-
8.
Overpower AT 4.5 1.4 1.2 See note 3 See note 4 9.
Pressurizer Pressure-Low 3.1 0.71 1.5
>1870 psig
>1859 psig l
1 i
10.
Pressurizer Pressure-High 3.1 0.71
- 1. 5 12380 psig 12391 psig 11.
Pressurizer Water Level-High 5.0 2.18 1.5 192% of instrument 193.8% of instrument I
span span 12.
Loss of Flow 2.5 1.0 1.5
>90% of loop
>89.2% of loop
{
design flow
- design flow
- t Loop design flow = 98,000 gpm RTP = RATED THERMAL POWER
}
i i
}
t
?
.f -
c h
TABLE 2.2-1 (continued) l r
l REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS' l
- =
}
e l
c Total l
}
Functional Unit Allowance (TA)
Z S
Trip Setpoint Allowable Value 13.
Steam Generator Water 12.0 9.18 1.5
>12% of span from
>10.2% of span from Level Low-Low D to 30% RTP D to 30% RTP increasing lin-increasing linearly jz l
early to >30.0% of to >28.2% of span l
t.
j span from 30% to froi 30% to 100%
FS
~
100% RTP RTP
', c p:.
14.
Steam /Feedwater Flow Mis-16.0 13.24 1.5/
<40% of full
<42.5% of full
~fi.
}
Match Coincident With 1.5 iteam flow at RTP iteam flow at RTP j'
Steam Generator Water Level 12.0 9.18 1.5
>12% of span from
>10.2% of span from
'?
Low-Low B to 30% RTP D to 30% RTP-
'l increasing lin-increasing linearly i
to >28.2% of span l
early to >30.0% of span from 30% to froi 30% to 100%
100% RTP RTP 15.
Undervoltage - Reactor 2.1 1.2$
0.23
>4830 volts
>4760 Coolant Pump' 16.
Underfrequency - Reactor 7.5 0
O.1
->57.5 Hz
->57.1 Hz i
Coolant Pumps
{
17.
Turbine Trip A.
Low Trip System Pressure NA NA NA
>800 psig
>750 psig
=
g B.
Turbine Stop Valve NA NA -
NA
>1% open
>1% open
=
Closure l
r i!F s~
RTP'= RATED THERMAL POWER j-
.. y 0
1 I
TABLE 2.2-1 (Continued) 1 REACTOR TRIP' SYSTEM INSTRUMENTATION TRIP SETPOINTS
.I-
=
e 3l NOTATION f'
c i<
l 5
NOTE 1: OVERTEMPERATURE AT lJ a
p
[T - T'-] + K (P ' P') - f (AI))
P AT 5 AT, { K
-K 2
3 3
5,
}
Where:
AT I
Measured AT by RTD Manifold Instrumentation
=
[
AT, Indicated AT at RATED' THERMAL POWER
{'
=
}
K
=
i 1.090
~i K
=
2 0.01450 4
I * S
'?.
1+TS The function generated by the lead-lag control'1er for T
=
o 2
dynamic compensation avg ri, & T2 Time constants utilized in the lead-lag controller for T,yg, ti = 28 secs.,
=
T2 = 4 secs.
i T
Average temperature *F
=
T' 5 587.4*F Reference T,yg at RATED THERMAL POWER K
.0006728
=
3 r
f k
Pressurizer pressure, psig l
P
=
t-P' 2235 psig, Nominal RCS operating pressure
=
a 5
=
Laplace transform operator, sec 1
- i 2
.O
}
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i TABLE 3.3-4 (Continued)
- f 9
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS q
Total J
i kFunctionalUnit Allowance (TA]
Z i
-r S
Trip setpoint Allowable value
" 4.
STEAM LINE ISOLATION
~. Manual NA NA NA NA NA i
a 6
b.
Automatic Actuation Logic NA NA NA NA NA i
j and Actuation Relays l
c.
Reactor Building Pressure-3.0 0.71 1.5
-<6.35
-<6.61 High 2 d.
Steam Flow in Two Steamlines-20.0 13.16 1.5/
< a function
< a function defined High, Coincident with
- 1. 5 defined as as follows: A Ap t'
follows: A AP corresponding to 44%
corresponding of full steam flow Y
to 40% of full between 0% and 20%
}
O steam flow load and then a Ap l
between 0% and increasing linearly 20% load and to a Ap corre-then a Ap sponding to 114.0%
increasing of full steam linearly to a flow at full load.
l Ap correspond-ing to 110% of l
full steam flow
^
at full load T,yg - Low-Low 4.0 1.12
- 1. 2 1553*F 1550.6*F II) e.
Steamline Pressure - Low 20.0 l
10.71 1.5 1675 psig 1635 psig l_
(1) Time constants utilized in lead lag controller for. steamline pressure low are as follows:
l Ta 1 50 secs.
In < 5 secs.
i 1
I
s -
l i
i 1
TABLE 3.3-4 3
- l m
Functional Unit Total Allowance (TA)
Z_
S Trip Setpoink Allowable Value C5 5.
TUR81NE TRIP AND FEEDWATER ISOLATION
/
w a.
Steam Generator Water 5.0 2.18 1.5
<82.4% of
<84.2% of narrow liarrow range range instrument Level - High-High instrument span span 6.
EMERGENCY FEEDWATER
~
l a.
Manual NA NA NA NA NA b.
Automatic Actuation Logic NA NA NA NA NA R
c.
Steam Generator Water 12.0 9.18 1.5
>12% of span
~>10.2% of span from Level - Low-Low from 0% to 30%
0% to 30% RTP in-Y RTP increasing creasing linearly to linearly to
>28.2% of span fron l
>30.0% of span 30% to 100% RTP from 30% to 100%
RTP i
j
- d. & f.
Undervoltage-ESF Bus
>5760 Volts with
>5652 Volts wit'h a i
4 a <0.25 second
<0.275 second time tiime delay 3elay
>6576 volts with
>6511 volts with a i.
a <3.0 second
<3.3 second time k
tiime delay Belay F
1 i
i
,