ML20236K843
| ML20236K843 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/06/1998 |
| From: | Skay D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20236K846 | List: |
| References | |
| NUDOCS 9807100104 | |
| Download: ML20236K843 (14) | |
Text
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51 UNITED STATES g
j NUCLEAR REGULATORY COMMISSION
\\.....[2 WASHINGTON, D.C. mi COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 1
LASALLE COUNTY STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 129 Ucense No. NPF-11 1.
Tne Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated November 24,1997, as supplemented on April 16,1998, complies l
with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformit) with the application, the provisions of the Act, I
and the regulations of the Commission;
=
C.
There is reasnnable 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; O.
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 i
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 enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-11 is hereby amended to read as follows:
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9907100104 990706 PDR ADOCK 05300373 Y
2 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
129, and the Environmental Pmtection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented prior to restari from L1F35.
FOR pNUCLEAR REGULATORY COMMISSION w 7 ]IE 7
Donna M. F*ry, Project Manag l
' Project Dir6acrate ill-2 j
Division of Reactor Projects - lil/lV
{
Office of Nuclear Reactor Regalation -
I
Attachment:
Changes to the Technical Specifications Date of issuance:
July 6, 1998 7
f l
[
t
i l
ATTACHMENT TO LICENSE AMENDMENT NO.129 FACILITY OPERATING LICENSE NO. NPF-11
_ DOCKET NO.60-373 i
Replace the following pages of the Appendix "A" Technical Specifications with the en61osed pages. The revised pages are identified by amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT
]
3/4 3-12 3/4 3-12 3/4 3-12a
{
3/4 3-13 3/4 3-13
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3/4 3/15 3/4 3-15 l
3/4 3-15a l
3/4 3-16 3/4 3-16 l
3/4 3-17 3/4 3-17 3/4 3-18 3/4 3-18 3/4 3-19 3/4 3-19 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 I
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ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME f~
TRIP FUNCTION RESPONSE TIME (Seconds)#
A.- AUI'OMATIC INITIATION 1.
PRIMARY CONTAINMENT ISOLATION a.
- 1)
Low, Level 3 N/A
- 2).
Low Low, Level 2 N/A 3)
Low Low Low, Level 1 s 1.0*, M b.
Drywell Pressure - High N/A c.
DELETED 2)
Pressure - Low s 2.0*, #
l 3)
Flow - High s 0.5*, M d.
DELETED e.
Condenser Vacuum -' Low N/A f.
Main Steam Line Tunnel Temperature - High N/A l
2.
SECONDARY CONTAINMENT ISOLATION N/A i
a.
Reactor Building Vent Exhaust Plenum Radiation - High b.
Drywell Pressure - High c.
Reactor Vessel Water Level - Low, Level 2 d.
Fuel Pool Vent Exhaust Radiation - High~
i 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION N/A 1
a,
' AFlow - High b.
- Heat Exchanger Ares, Temperature - High c.
Heat Exchanger Area Ve.dilatic 1 AT-High d.
SLCS Initiation e.
Reactor Vessel Water Level - Low Low, Level 2 f.
Pump and Valve Area Temperature - High g.
Pump and Valve Area Ventilation AT-High h.
Holdup Pipe Area Temperature - High i.
Holdap Pipe Area Ventilation AT-High J.
Filter / Demineralized Valve Room Aree Temperature - High k.
Filter / Demineralized Valve Room Area Ventilation AT-High I.
Pump Suction Flow - High 4.
REACTOR CCRE ISOLATION COOLING SYSTEM ISOLATIOM N/A a.
RCIC Steam Line Flow High b.
RCIC Steam Supply Pressure - Low
- c. '
RCIC Turbine Exhaust Diaphragm Pressure - High d.
RCIC Equipment Room Temperature - High e.
RCIC Steam Line Tunnel Temperature - High I
f.
F.OIC Steam Line Tunnel Temperature - High I
c.
Drywell Pressure - High h,
RCIC Equipment Room Temperature - High 5.
Deleted.
l LA SALLE - UNIT 1 3/4 3-18 Amendment No. 129 L _ _ _ _ ___ = _ _ _ -. _ - - _ _
TABLE 3.22.2-3 (Continuea)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)'
6.
RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION N/A a.
Reactor Vessel Water Level-Low, Level 3 b.
Reactor Vessel (RHR Cut-in Permissive) Pressure - High I
c.
RHR Pump Suction Flow-High l
B. MANUAL INITIATION N/A 1.
Inboard Valves 2.
Outboard Valves 3.
Inboard Valves 4.
Outboard Valves 5.
Inboard Valves 6.
Outboard Valves 7.
Outboard Valva TABLE NOTATIONS Isolation system instrumentation response time for MSIVs only. No diesel generator delays assumed.
Isolation system instrumentation response time specified for the Trip Function actuating the MSIVs shall be added to MSIV isolation time to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.
Sensor is eliminated from response time testing for the MSIV actuation logic circuits.
Response time festing and conformance to the administrative limits for the remaining channel including trip unit and relay logic are required.
N/A Not Applicable.
LA SALLE - UNIT 1 3/4 3-19 Amendment No.129
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