ML20106C430
| ML20106C430 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/12/1984 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20106C433 | List: |
| References | |
| NUDOCS 8410240164 | |
| Download: ML20106C430 (7) | |
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UNITED STATES f.. '
- p NUCLEAR REGULATORY COMMISSION 3
E WASHINGTON. D. C. 20555 d
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- ...o SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET =NO. 50-395 VIRGIL C. SUMMER-NUCLEAR STATION, UNIT NO. 1
-AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 28 License No. NPF-12 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A. ~ The application for amendment to the Virgil C. Summer Nuclear Station, Unit No.1 (the facility) Facility _0perating License No. NPF-12 filed by the South Carolina Electric & Gas Company acting for itself and South Carolina.Public Service Authority (the licensees), dated July 22, 1983, complies with the standards and requirements of the Atomic Energv Act of 1954, as amended (the Act) and the Comission's regulations s set forth in 10 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 Commission; C.
There'is tcasonable 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 Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; E.
The issuance of this license 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 hereby amended by.page changes to the Technical 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 to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 28, are hereby incorporated into this license.
South Carolina Electric & Gas Company shall operate the facility in accordence with the Technical Specifications and the Environmental Protection Plan.
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3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
'wa..l.b~R{;_6ix f: I
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..1,. Elinor G. Adensam, Chief
(
Licensing Branch No. 4 Division of Licensing
Enclosure:
Technical Specification Changes Date of Issuance: October 12, 1984 s
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ATTACHMENT TO LICENSE AMENDMENT NO. 28 FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. To maintain document completeness, the corresponding overleaf pages are also provided.
Amended Overleaf Page Page 2-8 2-7 2-9 2 - 10 Delete page 2 - 11 e
TABLE 2.2-1 (continued) c2 3
E}
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS e
Total functional Unit Allowance (TA)
Z S
Trip Setpoint Allowable Value c-18.
Safety Injection Input NA NA NA NA NA from ESF 19.
Reactor Trip System Interlocks A.
Intermediate Range NA NA NA 31 x 10 10 amps 16 x 10 11 amps Neutron flux, P-6 B.
Low Power Reactor Trips
^
Block, P-7 a.
P-10 input 7.5 4.56 0
P-13 input
- 7. 5 4.56 0
$10% turbine
$12.2% of turbine'
'?
impulse pressure impulse pressure equivalent equivalent C.
Power Range Neutron
- 7. 5 4.56 0
138% of RTP
$40.2% of RTP Flux P-8 0.
Low Setpoint Power 7.5 4.56 0
110% of RTP 17.8% of RTP Range Neutron Flux, P-10 E.
Turbine Impulse Chamber 7.5 4.56 0
<10% turbine
<12.2% turbine Impulse pressure pressure equivalent Pressure, P-13 equivalent 20.
Reactor Trip Breakers NA NA NA NA NA 21.
Automatic Actuation Logic NA NA NA NA NA i
RTP = RATED THERMAL POWER
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p TAllLE 2.2-1 (Continued) g REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS
[.
NOTATION h
NOIE 1:
OVERTEMPERATURE AT AT 5 AT,{K - K
[T - T'] + K (P - P') - f (al))'
i 2
3 t
Measured AT by RID Manifold Instrumentation Where:
AT
=
AT, Indicated AT at RATED THERMAL-POWER
=
K
= 1.090 i
K
= 0.01450 2
f The function generated by the lead-lag controller for T,yg
=
dynamic compensation Time constant's utilized in the lead-lag controller for T,yg, t i = 33 secs.,
&T
=
13, 2
T2 = 4 secs.
Average. temperature *F T
=
T' 5 587.4"F Reference T,yg at RATED THERMAL POWER
.0006728 K
=
3 Pressurizer pressure, psig P
=
g P'
2235 psig, Nominal RCS operating pressure
=
h S
=
Laplace transform operator, sec 1 n
M
+
4 TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEH INSTRUMENTATION TRIP SETPOINTS 9
NOTATION (Continued)
C g
NOIE 1:
(Continued) and f (AI) is a functior of the indicated difference betweer. top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:
(i) for q ~ 9 between - 34 percent and + 8 percent f (AI) = 0 where qt and q are percent t
b b
RATED Tl!ERMAL POWER in the top and bottom halves of the core respectively, and qt + qb 8
total THERMAL POWER in percent of RATED THERMAL POWER.
(ii) for each percent that the magnitude of q q exceeds -34 percent, the AT trip setpoint
~
t b
shall be automatically reduced by 1.67 percent of its value at RATED THERMAL POWER.
(iii) for each percent that the magnitude of qt ~9 exceeds +8 percent, the AT trip setpoint b
shall be automatically reduced by 1.11 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 3.6 percent AT span.
NOTE 3:
OVERPOWER AT AT < AT,{K - Ks
) T - Ks [T - T"] }
I 4
g g
as defined in Note 1 Where:
AT
=
as defined in Note 1 AT
=
g 2
K 1.091 4
h K
=
3 0.02/ F for increasing average temperature and 0 for decreasing average temperature ao
,F 1[3 The function generated by the rate-lag controller for T,yg dynamic compensation
=
3 M
- - q TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 9
NOTATION (Continued)
C5 NOTE 3:
(Continued)
Time constant utilized in the rate-lag controller for T,yg, r '= 10 secs.
=
T3 a
0.001190/ F for T > T" and Kc = 0.for.T-1 T"
^
Ks
=
as defined in Note 1 T
=
I" 587.4 F Reference T,yg at RATED THERMAL POWER as defined in Note-1 S
=
NOTE 4:
The channel's maximum trip setpoint shall not exceed its computed trip point by more than 2.7 percent AT span.
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