ML20028D442
| ML20028D442 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/28/1982 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20028D443 | List: |
| References | |
| NUDOCS 8301190128 | |
| Download: ML20028D442 (5) | |
Text
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SOUTH CAROLINA ELECTRIC 3 GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER HUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 8 License No. NPF-12 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Virgil C. Summer Nuclear Station, Unit No.1 (the facility) Facility Operating License No. NPF-12 filed by the South Carolina Electric & Gas Company acting for itself and South Carolina Public Service Authority (the licensees), dated December ?.8.1982, conplies 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 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 reasonable assurance: (1) 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 De 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 common 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 change to the Technical Spec-ifications as indicated in the attachments to this license amendment.
Partgraph 2.C(2) of Facility Operating Liccnse 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. 8, are hereby incorporated inta this license.
South 8301190128 830112 PDR ADOCK 05000395 OFFic p PDR stonaO omy NRC FORM 318 (10-80) NRCM Cao OFFlCIAL RECORD COPY uso m an.-m.wo
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Carolina Electric A Gas Company shall operate the facility in accord-ance with the Technical Specifications and the Envirorrnental Protection Plan.
3.
This license amendment is effective December 28, 1932.
FOR THE NUCLEAR REGULATORY C0:1i41SS10N 4
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' Elinor G. Mensan, Chief Licensing Branch No. 4 Division of Licensing i
Enclosure:
Techntcal Specification Changes i
l Date of Issuance: January 12, 1983 i
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ATTACH!!ENT TO LICENSE AMENDf!ENT NO. 8 FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following page of the Appandix "A" Technical Specifications with the enclosed page.
The revised pages areidentified by Amendment number and i
contain vertical lines indicating the area of change.
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l TABLE 3.6-1 (Continued) vs E
CONTAINMENT ISOLATION VALVES M
MAXIMUM VALVE NUMBER ISOLATION TIME E
A.
PHASE "A" ISOLATION (Continued)
FUNCTION (SEC) 31.
9312A-SS Sampling Line Supply Return From Radiation Monitor 40 32.
93128-55 Sampling Line Return Return From Radiation Monitor 40 33.
9339-S5 Sample Return Line To PRT 40 34.
9341-55 Sample Return Line To Pk(
40 35.
9356A-S3 Samplirg Line From Pressurizer 40 36.
93568-55 Sampling line From Pressurizer 40 37.
9357-55 Sampling Line From Pressurizer 40 38.
9364B-5S Sampling Lines From Reactor Coolant Loop B 40 39.
93658-55 Sampling Lines From Reactor Coolant Loop B 40 40.
9364C-SS Sampling Lines From Reactor Coolant Loop C 40 41.
9365C-SS Sampling Lines From Reactor Coolant Loop C 40 42.
9387-55 Sampling Line From Accumulators 40 Rf 43.
9398A-SS # (3)
Sampling Line From Steam Generator A Blowdown 40 44.
93988-55 # (3)
Sampling Line From Steam Generator B Blowdown 40 T
45.
9398C-SS # (3)
Sampling Line From Steam Generator C Blowdown 40 46.
7126-WL Reactor Coolant Drain Tank Vent Header 40 47.
7150-WL Reactor Coolant Drain Tank Vent Header 40 48.
1003-WL Reactor Coolant Drain Tank Discharge To Waste 40 49.
7136-WL Reactor Coolant Drain Tank Discharge To Waste 40 B.
PHASE "B" ISOLATION 1.
9568-CC Component Cooling To R. C. Pumps Bearings 60 g
2.
9600-CC Component Cooling To R. C. Pumps 60 g
3.
9605-C Component Cooling From R. C. Pumps Bearings 60 g
4.
9606-CC Component Cooling From R. C. Pumps Bearings 60 g
5.
1633A-FW #
Chemical Feed Line To Feedwater Loop A 60 6.
1633B-FW #
Chemical Feed Line To Feedwater Loop B 60 n
g 7.
1633C-FW #
Chemical Feed Line To Feedwater Loop C 60 m
C.
REACTOR BUILDING PURGE SUPPLY AND EXHAUST ISOLATION 1.
0001A-AH Reactor Building Purge Supply 5
2.
00018-AH Reacto Building. Purge Supply 5
3.
0002A-AH Reactor Building Purge Exhaust 5
. = _
TARLE 3.6-1 (Continued)
E CONTAINMENT ISOLATION VALVES MAXIMUN s
c:
VALVE NUMBER ISOLATION TIME F.
CHECK FUNCTION (SEC)
{
s 1.
7541-AC CRDM Coolant Water Inlet Line N/A 2.
7544-AC CRDM Coolant Water Outlet Line N/A 3.
9570-CC Component Cooling To R. C. Pump Bearings N/A 4.
9689-CC Component Cooling From R. C. Pump Bearings N/A 5.
8103-CS Reactor Coolant Pump Seal Water Return N/A i
6.
8368A-CS Seal Injection To R. C. Pump A N/A 7.
83688-CS Seal Injection To R. C. Pump B N/A 8.
8368C-CS Seal Injection To R. C. Pump C N/A 9.
8381-CS Charging Line To Regenerative Heat Exchanger N/A 10.
6799-FS Fire Service Deluge To Charcoal Filters N/A 11.
2661-IA Instrument Air Supply To Reactor Building N/A ca 12.
6588-NG Nitrogen Supply To Steam Generators N/A 1
13.
8046-RC Pressurizer Relief Tank Makeup Water Line N/A
.cn 14.
2913-SA Service Air Supply To Reactor Building N/A A
15.
3009A-SP Supply To Reactor Building Spray Nozzles N/A R
16, 3009B-55 Supply To Reactor Building Spray Nozzles N/A 17.
8947-S1 Accumlator Nitrogen Supply N/A 18.
8861-SI Fill Line To Accumulators N/A Valve not subject to Type "C" leakage test.
(1) Manual valves may be opened on an intermittent basis under administrative control.
k (2) Remote tr.inual valve positious.irr maintained by administrative control.
8 (3) The pro isions of Specification 3.0.4 are not applicable from December 28, 1982, until July 1, 1983.
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