ML20126F399
| ML20126F399 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/15/1992 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20126F396 | List: |
| References | |
| NUDOCS 9212300289 | |
| Download: ML20126F399 (8) | |
Text
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UNITED STATES
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SOUTH CAROLINA ILECTRIC & GAS COMPANY ji.0_QTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 yjRGil L.
SUMMER NVCLEAR STATION. 1) SIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 108 License No. NPF-12 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by South Carolina Electric & Gas Company (the licensee), dated December 15, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commis3'~ '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 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 be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be-inimical to the common 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:
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. (2)
Technical-Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 108
, and the Environmental 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 amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam,- Director Project Directorate 11-1 Division of Reactor Projects - I/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 15, 1992
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ATTACHMENT T0 LICENSE AMENOMfNT NO 108 -
TO FACILITY OPERATING llCENSE NO. NPF-ll' QQ.CKET NO 50-395 Replace the following pages of the ' Appendix A' Technical Specifications with-l the enclosed pages,' The-revised pages are indicated by-marginal lines.
Remove Paaes Insert Paaes 3/4 3-29 3/4.3-29 3/4 3-30 3/4 3-30 3/4 3-31 3/4 3 3/4 3-33 3/4 3-33 3/4 3-34 3/4 3-34 E
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INSTRUMENTATION TABLE 3.3-5.
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS.
1.
Manual a.
Safety Injection Not Applicable b.
Reactor Building Spray Not Applicable c.
Containment Isolation
'Not Applicable Phase "A" Isolation d.
Steam Line Isolation Not Applicable e.
Feedwater Isolation Not Applicable f.
Emergency Feedwater Not Applicable 9
Essential Service Water Not Applicable h.
Reactor Building _ Cooling _ Fans Not Applicable 1.
Control Room Isolation Not Applicable 2.
Reactor Buildina Pressure-High a.
Safety Injection (ECCS) 527..,'2)/27.0(I) b.
Reactor Trip (from Si) 53.0 c.
Feedwater Isolation
$10.0 d.
Containment Isolation-Phase "A" -
_545.0(4)/55.0(5)
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-SUMMER - UNIT 1 3/4 3 Amendment No. 108
..y INSTRUMENTATION-TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS e.
Reactor Building Purge and Not Applicable Exhaust Isolation f.
Emergency Feedwater Pumps Not Applicable g.
Service Water System 71.5(4)/81.5(5) h.
Reactor Building Cooling Units 76.5(4)/86.5(5) 1.
Control Room Isolation Not Applicable 3.
Pressurizer Pressure-Low a.
Safety Injection (ECCS) 527.0(2)/27.0(1) b.
Reactor Trip (from SI) 53.0 c.
Feedwater Isolation
$10.0 d.
Containment Isolation -Phase "A" 545.0(4)/55.0(5) e.
Reactor Building Purge and Not Applicable ~
Exhaust Isolation f.
Emergency Feedwater Pumps Not Applicable 9
Service Water System 71.5(4)/81.5(5) h.
Reactor Building Cooling Units 76.5(4)/86.5(5) 1.
Control Room Isolation Not Applicable 4.
Differential Pressure Between Steam Lines-Hich a.
Safety Injection (ECCS) 527.0(2)/37.0(3) b.
Reactor Trip (from SI) 53.0 c.
Feedwater Isolation
$10.0 d.
Containment Isolation -Phase "A"
$45.0(4)/55.0(5) i l
l SUMMER - UNIT 1 3/4 3-30 Amendment No. E7, 108 1
.f INSTRUMENTATION TABLE 3,3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS e.
Reactor Building Purge and Not Applicable Exhaust Isolation f.
Emergency feedwater Pumps Not Applicable g.
Service Water System 571.5(4)/81.5(5)-
h.
Reactor Building Cooling Units
$76.5(4)/86.5(5) 1.
Control Room Isolation Not Applicable 5.
Steam Line Pressure-Low a.
Safety Injection - ECCS 527.0(2)/37.0(3) b.
Reactor Trip (from SI) 53.0 c.
Feedwater Isolation
$10.0 d.
Containment Isolation - Phase "A"
$45.0(4)/55.0(5) e.
Reactor Building and Purge and Exhaust Isolation Not Applicable f.
Emergency feedwater Pumps Not Applicable g.
Service Water System 571.5(4)/81.5(5) h.
Reactor Building Cooling Units
$76.5(4)/86.5(5) 1.
Steam Line Isolation
$10.0 j.
Control Room Isolation Not Applicable 6.
Steam Flow in Two Steam Lines - Hiah Coincident with Tavg--Low-low a.
Steam Line Isolation 512.0 7.
Reactor Buildina Pressure-Hiah-2 a.
Steam Line Isolation 59.0 SUMMER' UNIT 1 3/4 3-31 Amendment No. $7,108
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INSTRUMENTATION TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 13.
Trip of Main Feedwater Pumps
- a. Motor-driven Emergency Not Applicable feedwater Pumps 14.
Loss of Power
- a. 7.2 kv Emergency Bus
$10.3 Undervoltage (Loss of Voltage)
- b. 7.2 kv Emergency Bus
$13.3 Undervoltage (Degraded Voltage) 15.
Containment Radioactivity--Hich
- a. Purge-and Exhaust Isolation Not Applicable 16.
RWST Level--Low-Low
- a. Automatic Switchover to Not Applicable Containment _ Sump 17.
Aux Feed Suction Pressure Low
- a. Suction transfer Not Applicable-Note:
Response time for Motor-160.0 driven Emergency Feedwater Pumps on all SI signal starts SUMMER - UNIT 1 3/4 3-33 Amendment No.108
j INSTRUMENTATION TABLE 3.3-5 (Continued)
TABLE NOTATION (1)
Diesel generator starting and sequence loading delays from under voltage included. Response time limit includes positioning of valves to establish $1 path and attainment of aischarge pressure for centrifugal charging pumps and RHR pumps. Sequential transfer of centrifugal charging pump suction from.the VCT to the RWST (RWST valves open, then VCT valves close) is.not included.
(2)
Diesel generator starting delay not included. Sequence loading delay included. Offsite power available.
Response time limit includes positioning of valves t0 establish SI path and attainment-of.
1 discharge pressure for centrifugal charging pumps.
Sequential l
transfer of centrifugal charging pump suction from the VCT to the RWST (RWST valves open, then VCT valves close)-is-included.-
(3)
-Diesel generator starting and sequence loading delays from under voltage included. Response time limit includes positioning of valves to establish SI path _and attainment of discharge pressure for centrifugal charging pumps. Sequential transfer of centrifugal charging pump suction from the VCT to the RWST (RWST valves open',
then VCT valves close) is included.
(4)
Diesel generator starting delay not included. Sequence loading delay included. Offsite power available.
(5)
Diesel generator starting and sequence loading delays from undervoltage included.
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SUMMER - UNIT 1 3/4 3-34 Amendment No.108 I