ML20033F592
| ML20033F592 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/15/1990 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033F593 | List: |
| References | |
| NUDOCS 9003220130 | |
| Download: ML20033F592 (11) | |
Text
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UNITED $TATES
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-g NUCLEAR REGULATORY COMMISSION i 5
-E WASHINGTON, D. C. 20$55
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SOUTH CAROLINA ELECTRIC & GAS COMPANY.
SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUl#1ER NUCLEAR STATION UNIT NO.- 1 AMENDMENT TO FACILITY OPERATING LICENSE Amende nt No. 90 License No. NPF-12 1.
The Nuclear Regulatory Commission (the Commission) has found thati A.
The application for amendment by South Carolina Electric & Gas Comparty (the licensees), dated July 21, 1989, as supplemented December 11', 1989 January 2,1990 and February 6,.1990, conplies with the standards and req)uirements of the Atomic Energy Act of 1954, as amended (the Act, and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Connission; 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 conpliance with the Commission's regulations; e
- D.
The issuance of this amendment will not be inimical to the comon defense and security or to.the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical
. Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-12 is hereby amended to read as follows:
9003220130 900315 PDR ADOCK 05000395 P
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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as. revised through Amendaent No. 90
,. and the Environnental Protection Plan contained in Appendix B, are hereby incorporated in the license.
South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental
- Protection Plan.
3.
This anendwent is effective as of its date of issuance, and shall,be implenented on restart following the March 23, 1990 refueling outage and prior to entering the modes specified in Tables 3.3-1 and 3.3-3 as applicable for the changes in this amendnent.
FOR THE NUCLEAR REGULATORY COMMISSION l
L
(
Lester Kintner/for Elinor G. Adensam, Director Project Directorate II I Division of Reactor Projects I/II l
Attachment:
Changes to the Technical Specifications Date of Issuance: March 15,1990 t
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- SEE PREVIOUS CONCURRENCE
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0FFICIAL RECORD COPY
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- ATTACWENT TO LICENSE ' AMENDMENT NO. 90 TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 l
Replace the following sages of the Appendix "A" Technical Specifications with 4
.the enclosed pages.
T1e revised pages are identified by amendment nunber and contain vertical ' lines indicating the areas of change.
.l Renove Pages Insert-Pages
~ 2-5 2-5 2-8 2-8 2 2-9 i
2-10 2-10 1
B 2-5 82-5.
1 3/4 3-9 3/4 3-9
.i 3/4 3-27 3/4 3-27
'l 3/4 3-28b 3/4 3-28b l
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w TABLE 2.2-1 C
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS Total E
Functional Unit Allowance (TA)
Z S
Trip Setpoint.
Allowable Value a
w 1.
Manual Reactor Trip Not Applicable NA NA NA NA 2.
Power Range, Neutron Flux 7.5 4.56 0
$109% of RTP-1111.2% of RTP High Setpoint Low Setpoint 8.3 4.56 0
<25% of RTP
' <27.2% of RTP 3.
Power Range, Neutron Flux 1.6 0.5 0
<5% of RTP with
<6.3% of RTP with High Positive Rate i time constant i time constant 12 seconds 22 seconds
-4.
Power Range, Neutron Flux
- 1. 6 0.5 0
<5% of RTP with
<6.3% of RTP with High Negative Rate i time constant i time constant m
Ji 22 seconds 22 seconds 5.
Intermediate Range, 17.0 8.4 0
125% of RTP
$31% of RTP Neutron Flux 6.
Source Range, Neutron Flux 17.0 10.0 0
$105 cps
$1.4 x 105 cps 7.
Overtemperature AT 9.8 7.21
- 1. 6 See note 1 See note 2
& 1.2**
y 8.
Overpower AT 5.2 1.96 1.6 See note 3 See note 4 R
9.
Pressurizer Pressure-Low 3.1 0.71
- 1. 5 11870 psig 11859 psig E.
10.
Pressurizer Pressure-High 3.1 0.71 1.5
$2380 psig
$2391 psig k 11.
Pressurizer Water Level-High 5.0 2.18
- 1. 5 192% of instrument'
<93.8% of instrument span span m
12.
Loss of Flow 2.5 1.48
.6
>90% of loop
>88.9% of loop p
design flow
- design flow
- 8
- Loop design flow = 96,500 gpm RTP - RATED THERMAL POWER
- 1.6% span for Delta-T (RTDs).and 1.2% for Pressurizer Pressure.
l
TABLE'2.2-1 (Continued) v, REACTOR TRIP ~ SYSTEM INSTRUMENTATION TRIP SETP0iNTS NOTATION E
Q ' NOTE 1:
OVERTEMPERATURE AT AT 5 AT,[K K
[T - T'] + K (P - P') - f (AI)]
1 2
3 3
1 Where:
AT Measured AT by RTD Instrumentation
=
AT, 5
Indicated AT at RATED THERMAL POWER K
5 1.203' 1
K 1
0.03006 2
1
- I'b 1+TS The function generated by the lead-lag controller for T
=
m d3 2
dynamic compensation
- 9 Time constants utilized in lead-lag controller for T,yg, T1 1 28 secs,,
T1, T2
=
T2 5 4 secs.
T Average temperature, "F
=
i T'
5 587.4*F Reference T,yg at RATED' THERMAL POWER K3 1
0.00147 P
Pressurizer pressure, psig
=
E P'
1 2235 psig, Nominal RCS operating pressure 2
l 5
S Laplace transform operator, sec 1
=
E.
1
- m
TABLE 2.2.-1 (Continued)
.c f
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 9
NOTATION (Continued) i C
2i NOTE 1:
(Continued) a and f (AI) is a function of the indicated difference between top and bottom detectors of the t
power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:
(i) for g 9 between - 24 percent and + 4 percent f t
b t (AI) = 0 where q and q are percent:
t b
RATED THERMAL POWER in the top and bottom halves of the core respectively, and q *9 IS t
b total THERMAL POWER in percent of. RATED THERMAL POWER.
(ii) for each percent that the magnitude of q ~9b exceeds -24 percent, the AT trip setpoint t
shall be automatically reduced by 2.27 percent of its value at RATED THERMAL POWER.
m d>
(iii) for each percent that the magnitude of q t
gb exceeds +4 percent, the AT trip setpoint shall be automatically reduced by 2.13 percent of its value at RATED THERMAL POWER.
NOTE 2:
The channel's maximum trip setpoint shall not exceed its computed trip point by more than 2.2 percent AT Span.
g NOTE 3:
OVERPOWER AT g
AT 1 AT [K
-K T - Ks [T - T"))-
4 3
(y s3 g
E Where:
AT as defined in Note 1
=
s AT as defined in' Note 1
=
F K
5 1.0875 4
E K
0.02/ F for increasing average temperature and 0 for decreasis.g average 3
temperature 8
y a3 The function generated by the rate-lag controller for T,yg dynamic compensation
=
- ;fC
, =,
1 TABLE'2.2-1 (Continued)'
~ REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS le
~ NOTATION (Continued)
E
-d NOTE 3 (continued) w Ta Time constant utilized in the rate-lag contro11er'for.T,g, r3 >
=
10 secs.
3 Ks 0.00156/ F for T >-T" and Ks = 0 for T < T" T
=
as defined in Note 1 T"
587.4"F Reference T at RATED THERMAL POWER avg S
as defined in Note 1
=
NOTE 4:
The channel's maximum trip setpoint shall not exceed its computed trip point by more than 2.4 percent AT Span.
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' LIMITING SAFETY' SYSTEM SETTINGS I
1 BASES Intermediate and Source Range, Nuclear Flux (Continued) uncontrolled rod cluster control assembly bank withdrawal from a suberitical condition.
These trips provide redundant protection to the low setpoint trip 1
of the Power ~ Range, Neutron' Flux channels.
The. Source Range channels will
' initiate a reactor trip at about 10+5 counts per second unless manually blocked when P-6 becomes active. The purpose of the P-6 setpoint, which is above the lower end of the intermediate range scale, is to give the operators sufficient time to actuate the source range reactor trip block. -The Intermediate Range channels will initiate a reactor trip at approximately 25 percent of. RATED
. THERMAL POWER unless manually blocked when P-10 becomes active.
'Overtemperature AT 4
The Overtemperature delta T trip provides core protection to prevent DNB for all combinations of pressure, power, coolant temperaturs, and axial power distribution, provided that the transient is slow with respect to piping transit' delays from the core to the temperature detectors (about 2 seconds)
T plus thermal delays associated with the RTD's mounted in the thermowells
.(about 5 seconds),'and pressure is within the range between.the Pressurizer high and low pressure trips.
The setpoint is automatically varied with 1)-
coolant temperature to correct for temperature induced changes in density and heat capacity of' water and includes dynamic compensation for piping delays from the core' to the loop temperature detectors, 2) pressurizer pressure, and 3) axial power distribution. With normal axial power distribution, this reactor trip limit is always below the core safety limit as shown in Figure 2.1-1.
If axial peaks are greater than design, as indicated by the difference between top-and bottom power range nuclear detectors, the reactor trip is automatically reduced according to the notations in Table 2.2-1.
Overpower AT The Overpower delta T trip provides assurance ~ of fuel integrity (e.g., no
' fuel melting and less than 1 percent cladding strain) under all possible overpower conditions, limits the required range for Overtemperature delta T protection, and provides a backup to the High Neutron Flux trip.
The setpoint is automatically varied with 1)= coolant temperature to correct for temperature induced changes in density and heat capacity of water, and 2) rate of change of temperature for dynamic compensation for piping and thermal delays from the core to the loop temperature detectors to ensure that the allowable heat gener-ation rate (Kw/ft) is not exceeded.
The overpower AT trip provides protection to mitigate the consequences of various size steam breaks as reported in WCAP 9226, " Reactor Core Response to Excessive Secondary Steam Break."
Pressurizer Pressure In each of the pressure channels, there are two independent bistables, each with its own trip setting to provide for a high and low pressure trip thus limiting the pressure range in which reactor operation is permitted.
The low setpoint trip protects against low pressure which could lead to DNB by tripping the reactor in the event of a loss of reactor coolant pressure.
SUMMER - UNIT 1 B 2-5 Amendment No. 44, 90
=
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s TABLE 3.3-2
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v.
REACTOR TRIP SYSTEM' INSTRUMENTATION RESPONSE TIMES n
EE FUNCTIONAL UNIT RESPONSE TIME-4 s
1.
Manual Reactor Trip Not Applicable 2.
Power Range, Neutron Flux
$ 0.5 seconds (1) 3.
Power Range, Neutron Flux, High Positive Rate Not Applicable
.s 4.
Power Range, Neutron Flux, High Negative Rate 5 0.5 seconds (1) l S.
Intermediate Range, Neutron Flux R
Not Applicable
{
6.
Source Range, Neutron Flux Not Applicable 7.
Overtemperature AT
$ 8.5 seconds (1)(2) 8.
Overpower AT
$ 8.5 seconds (1)(2) 9.
Pressurizer Pressure--Low
$ 2.0 seconds 10.
Pressurizer Pressure--High 5 2.0 seconds 11.
Pressurizer Water Level--High Not Applicable b*
Et (1) Neutron detectors are exempt from response time testing.
Response time of the neutron flux signal portion-of the channel shall' be measured from detector output or input of first electronic component in channel.
w
? (2)The 8.5 second response time includes a 5.0 second delay for the RTDs mounted in thermowells.
8 t
9
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TABLE 3.3-4 (Continued)
-g 3
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 9
Total Functional Unit Allowance (TA)
Z
- Sj Trip Setpoint Allowable Value
[
4.
STEAM LINE ISOLATION a.
Manual NA NA NA NA NA' b.
Automatic Actuation Logic NA NA NA' NA NA-and Actuation Relays 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 followsi A Ap w
follows: A AP corresponding to 44%
1 corresponding of full steam flow w
to 40% of full
.between 0% and 20%
m steam flow' load and then a Ap' between 0% and increasing linearly 20% load and to a op corre-then a op sponding to 114.0%
increasing of full steam
. linearly to a flow at full load.
Ap correspond-ing to 110% of full steam flow at full load F
T
- Low-Low 4.0
.71
.8 2552.0 F 1548.4*F l
a>
avg i
e.
Steamline Pressure - Low 20.0 10.71 1.5
>675 psig
>635 psig(1)
?
Y (1) Time constants utilized in lead lag controller for steamline pressure low are as follows:
1 1 50 secs-T2 < 5 secs.
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6-2 TABLE 3.3-4 (Continued) u, C
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS Total E ' Functional Unit Allowance (TA)
Z S
q
~
^
Trip'Setpoint Allowable Value
?
g 9.
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS INTERLOCKS a.
Pressurizer' Pressure, P-11 3.1
.71 1 1.5 1985 psig
~21974 psig &
11996 psig b.
T,yg Low-Low, P-12 4.0
.71
.8 552*F.
1548.4*F & 1555.6*F w
c.
Reactor Trip, P-4 NA NA NA NA NA D
Y M
e R
a-O
_-