ML20084A846
| ML20084A846 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/16/1984 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20084A850 | List: |
| References | |
| NUDOCS 8404250298 | |
| Download: ML20084A846 (8) | |
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[o UNITED STATES g
NUCLEAR REGULATORY COMMISSION o
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j wAsmNGTON D.C.20555 g,*****j SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 i
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE 3
Amendment No. 23 License No. NPF-12 i
1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment to the Virgil C. Sumer 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 November 16, 1983, and supplemented January 6 and 25, 1984, complies with the standards and reouirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; 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 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 Comission's regulations and all applicable requirements have i
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 L!
paragraph 2.C(2) of Facility Operating License No. NPF-12 is hereby amended to read as follows:
j (2) Technical Specifications, The Technical Specifications contained in Appendix A, as revised through Amendment No. 23, are hereby incorporated into this license.
South Carolina Electric & Gas-Company shall operate the facility in accordance with the Technical Specifications and the Environmental j
Protection Plan.
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8404250298 840416 PDR ADOCK 05000395
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This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COM41SSION
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Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Enclosure:
Technical Specification Changes a
Date of Issuance: April 16, 1984 b
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ATTACHMENT TO LICENSE AMENDMENT NO. 23 4
FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 e
Replace the following pages of the Appendix "A" Techaical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding over-J 1eaf pages are also provided to maintain document completeness.
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Amended Overleaf Page Page VIII VII 3/4 7-9a B3/4 7-3 B3/4 7-4 y
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INDEX.
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity....................................
3/4 6-1 Containment Leakage......................................
3/4 6-2 Containment Air Locks....................................
3/4 6-4 Internal Pressure........................................
3/4 6-6 Air Temperature..........................................
3/4 6-7 Containment Structural Integrity.........................
3/4 6-8 Containment Ventilation System.....................s.....
3/4 6-11 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Reactor Building Spray System............................
3/4 6-12 Spray Additive System....................................
3/4 6-13 Reactor Building Cooling System..........................
3/4 6-14
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3/4 6.3 PARTICULATE IODINE CLEANUP SYSTEM........................
3/4 6-15 3/4.6.4 CONTAINMENT ISO LATION VALVES.............................
3/4 6-17 3/4,6.5 COMBUSTIBLE GAS CONTROL Hydrogen Monitors........................................
3/4 6-21 Electric Hydrogen Recombiners............................
3/4 6-22 f
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I INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE S a fe ty Va 1 v e s............................................
3/4 7-1 Emergency Feedwater System...............................
3/4 7-4 2'
Condensate Storage Tank..................................
3/4 7-6 Activity.................................................
3/4 7-7 I'
Main Steam Line Isolation Va1ves.........................
3/4 7-9 Feedwater Isolation Va1ves...............................
3/47-9al 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........
3/4 7-10 3/4.7.3 COMPONENT C03 LING WATER SYSTEM...........................
3/4 7-11 3/4.7.4 SERVICE WATER SYSTEM.....................................
3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK......................................
3/4 7-13 3/4.7.6 CONTROL ROOM NORMAL AND EMERGENCY AIR HANDLING SYSTEM....
3/4 7-14 3/4.7.7 SNUBBERS.................................................
3/4 7-16 3/4.7.8 SEALED SOURCE CONTAMINATION..............................
3/4 7-23 3/4.7.9. FIRE SUPPRESSION SYSTEMS Fire Suppression Water Systen............................
3/4 7-25 Sp ray and/o r Sp ri nkl e r Sys tems...........................
3/4 7-28
-CO System...............................................
3/4 7-30 2
Fire Hose Stations.......................................
3/4 7-31 Yard Fire Hydrants and Hydrant Hose Houses...............
3/4 7-33 3/4.7.10 FIRE RATED ASSEM8 LIES....................................
3/4 7-35 3/4.7.11 AREA TEMPERATURE MONITORING..............................
3/4 7-37 SUMMER-UNIT 1 VIII Amendment No. 23 l_
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PLANT SYSTEMS FEEDWATER ISOLATION VALVES LIMITING CONDITION FOR OPERATION
f APPLICABILITY:
MODES 1, 2, and 3 ACTION:
MODE 1 With one feedwater isolation valve inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; Otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUT 00WN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODES 2 With one feedwater isolation valve inoperable, subsequent and 3 operation in MODES 2 or 3 may proceed provided:
a.
The isolation valve is maintained closed.
b.
The provisions of Specification 3.0.4 are not applicable.
Otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.6 Each feedwater isolation valve shall be demonstrated OPERABLE by verifying full closure within 5 seconds when tested pursuant to Specification 4.0.5.
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1 SUMMER - UNIT 1 3/4 7-9a Amendment No. 23 ki
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PLANT SYSTEMS 4
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BASES 3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES i
The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture.- This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, O
and 2) limit the pressure rise within the reactor building in the event the i
steam line rupture occurs within the reactor building. The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses, t
3/4.7.1.6 FEEDWATER ISOLATION VALVES The OPERABILITY of the Feedwater Isolation Valves serves to (1) limit the effects of a Steam Line rupture by minimizing the positive reactivity effects of the Reactor Coolant System Cooldown associated with the blowdown, and (2) limit the pressure rise within the reactor building in the event of a Steam Line or Feedwater Line rupture within the reactor building.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70*F and 200 psig are based on the average impact valves of the steam generator material at 10*F and are sufficient to prevent brittle fracture.
3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that suf-L ficient cooling capacity is available for continued operation of safety related i1 equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.
3/4.7.4 SERVICE WATER SYSTEM
,J The OPERABILITY of the service water system ensures that sufficient cooling capacity is available for continued operation of safety related l.
equipment during normal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent.with the assumptions used in the accident conditions within acceptable limits.
Ji 3/4.7.5 ULTIMATE HEAT SINK l?
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The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) provide normal 4
cooldown of the facility, or 2) to mitigate the effects of accident conditions ll within acceptable limits.
I SUMMER - UNIT 1 B 3/4 7-3 Amendment No. 23 l-
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j BASES ULTIMATE HEAT SINK (Continued)
The limitations on minimum water level and maximum temperature are based on providing a 30 day cooling water ' supply to safety related equipment without exceeding their design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants", March 1974.
3/4.7.6 CONTROL ROOM NORMAL AND EMERGENCY AIR HANDLING SYSTEM The OPERABILITY of the control room ventilation system ensures that
- 1) the-ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel i
during and following all credible accident conditions.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A",10 CFR 50.
3/4.7.7 SNUB 8ERS 1
All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on-any safety-related system.
Snubbers are classified and grouped by design and manufacturer but not by 1;
size.
Forexample,mechanicalsnubbersutilizingthesamedesignfeaturesof D
the 2 kip,10 kip and 100 kip capacity manufactured by company A" are of the same type.
The same design mechanical snubber manufactured by company "B" for -
i the purposes of this specification would be of a different type, as would j
hydraulic snubbers from either manufacturer.
N The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.
Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined
<d by the number of inoperable snubbers found during an inspection.
Inspections performed before that interval has elapsed may be used as a new reference y?
- point to determine the next inspection.
However, the results of such early inspections performed before the original required time interval has. elapsed (nominal time less 25%) may not be used to : lengthen the required inspection I
interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
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