ML20213A667
| ML20213A667 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/14/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20213A664 | List: |
| References | |
| NUDOCS 8704280154 | |
| Download: ML20213A667 (2) | |
Text
.
[......
'o~g umTEDsTATas
[ *',
g
- g NUCLEAR REGULATORY COMMISSION t
W ASMINGTON, D. C. 20666 t,,.....,o SAFETY EVAlllATION BY THE OFFTCE OF NUCLEAR REACTOR REG RELATED TO AMENDMENT N0.65 TO FACILITY OPERATING LICEN S_00TH CAROLINA ELECTRIC & GAS COPPANY SOUTH CAROLINA PUMLIC SERVICE AUTHORITY VIRGIL C. SIMEp NUCLEAR STATION. UNIT N0.1 l
i DOCKET N0. 50-395 i
_ INTRODUCTION By letter dated January 8,1987, South Carolina Electric and Gas Company (the licenseel requested an amendment to the Technical Specifications.
i l
amendment would change the trip setpoint and the allowable value listed in The Setpoints" for the intemediate range compensated ion cha current (AMPS) to the equivalent percent indication.
changed to reflect percent indication and to provide further clarificationThe Bases regarding the P-6 setpoint. These changes would meet the aufdelines of Regulatory Guide 1.97 Revision 3 reouf rements for Post Accident Neutron Monitoring Instrumentation.
I EVALUATION i
The change to the Technical Specifications is beino submitted because of a l
i for Post Accident Neutron Monitoring Instrumentation.necessary mod replace the present non-post accident oua11fied Source Ranoe (SR) BF3This modif Class IE, post accident qualified fission chamber detectors, de l
detectors are as follows: Instrument ranges and scales of the existing detector l
l Detector BF3 Fission Chamber 0
6 0
6 SR 10 - 10 cps 10 - 10 g,,
IP 10*II - 10'3 amps 10 8 - 2x10 % Indication 2
This change is administrative in that no setooints are bein The current to the eouivalent percent indication.
l l
h[y[
D f
P
2 i
The equivalent values are based on tycical three loop Westinghouse plant I
da ta.
A check using V.C. Summer cycle 1 startup data we agreementwiththeselectedtypicalplantvalue(8.3x10'gperformedgodwasin indication).
vs 7.5x10' percent selectino Also, the slight difference is in the conservative direction by of 4.5x10'ghe typical plant value for the trip setooint.
The allowable value percent indication was obtained by interpolation. The NRC staff finds the intermediate range P-6 trip setpoint and allowable value equivalent acceptable.
t The change to the Bases which states that the P-6 setpoint is selected such that the operators will have sufficient time to actuate the source range i
reactor trio block is a clarifying statement.
Therefore, the NRC staff finds the Bases clarification regarding the P-6 trio setpoint acceptable.
l FNVIRONMENTAL CONSIDFRATION This amendment involves a chance in the installation of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has detemined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents i
-that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
i The Comission has previously issued a proposed finding that this amendment involves no significant ha:ards consideration and there has been no public coment on j
such findino.
Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Section $1.22(c)(91 10 CFR 51.22(b) no environmental impact statement or envittnmental Pursuant to assessment need be prepared in connection with the issuance of this amendment.
CONCLt!SION We have concluded, based on the considerations discussed above, thatt.
(11 there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Comission's regulations and the issuance of this amendment will not be inimical to the commen defense and security or to the health and safety of the public.
i Dated: April 14, 1987 Principal Contributors:
J. B. Popkins, Project Directorate #P, DPLA I
i