ML20129A906

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Amend 12 to License NPF-18,revising Tech Spec Table 3.3.2-2 to Change Main Steam Line Low Pressure Instrument Response Time from 1 to 2
ML20129A906
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 07/01/1985
From: Butler W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20129A910 List:
References
NUDOCS 8507150409
Download: ML20129A906 (4)


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UNITED STATES y'3m g

NUCLEAR REGULATORY COMMISSION

,j WASHINGTON, D. C. 20555

\\, s.......f COMMONWEALTH EDISON COMPANY DOCKET fl0. 50-374 LA SALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY CPERATING LICENSE Amendment No. 12 License No. NPF-18 1.

-The Nuclear Regulatory Comission (the Comission or the hRC) having found that:

A.

The application for amendment filed by the Comonwealth Edison Company cated June la, 1985, complies with the standarcs and requirements of the Atomic Energy Act of 1954, as arrended (the Act), and the Commission's regulctions set forth in 10 CFR Chapter.I; B.

The facility will operate in conformity with the application, the provisions of the Act ano the rules and regulations of the Cer mission; C.

There is reasonable assurance (i) that the activities cutberized 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 Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amencment will not be inimical to the common defense ana security or to the health and safety cf the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51

.of the Comission'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 arrendment and pa.agraph 2.C.(2) of Facility Operating License No NPF-18 is hereby amended to read as follows:

2.

Technical Specifications The Technical Specifications contained in Appendix A, as i

revised through Amendment No.12 and the Environmental frotection 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 Protect 10n ~

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0507150409 850701

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This license amendment is effective ds of June 20, 1985.

- FGk 1hE NUCLEAR REGULATORY C0fililSSICP llalter R. Butler, Chief L.icensing-Branch ho. 2 Division of Licensing

Attachment:

Changes to-the Technical Specifications Date of' Issuance: R 013 4

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ENCI OSL'RE TO LICENSE AMENDMENT NO.12 FACILITY OPERATIllG LICEflSE NO. NPF-18 DOCKET N0. 50-374 Replace the 'c11cving page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contain e vertical line indicating the area of change.

REMOVE INSERT 3/4 3-18 3/4 3-18 E

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1 TABLE 3.3.2-3 1

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESP 0'15E TIME (Seconds)#

A.

AUTOMATIC INITIATION 1.

PRIMARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level 1)

Low, Level 3 N.A.

g),,

2)

Low Low, Level 2 11.g*fs13 b.

Drywell Pressure - High

-<13 c.

Main Steam Line 1)

Radiation - High(b)

<1.0*/<13(a),,

72. 0*/713((*)),,

ss 2)

Pressure - Low a

70.5*/713 3)

Flow - High d.

Main Steam Line Tunnel Temperature - High fi. A.

e.

Condenser Vacuum - Low N.A.

f.

' Main Steam Line Tunnel a Terperature - High N.A.

2.

SECONDARY CONTAINMENT ISOLATION ReactorBuilding(gntExhaustPlenum

<13(3) a.

Radiation - High b.

Drywell Pressure - High 513ha

<13 Reactor Vessel Water Level - Low, Level (g) c.

d.

Fuel Pool Vent Exhaust Radiation - High 513(a) 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - High 113(a)##

b.

Heat Exchanger Area Temperature - High N.A.

c.

Heat Exchanger Area Ventilation AT-High N.A.

d.

SLCS Initiation N.AI) e.

Reactor Vessel Water Level - Low Low, Level 2 113 4.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION

<13(*)###

a.

RCIC Steam Line Flow - High b.

RCIC Steam Supply Pressure - Low 513(a) c.

RCIC Turbine Exhaus: Diaphragm Pressure - High N.A.

d.

RCIC Equ.ipment Room Temperature - High N.A.

e.

RCIC Steam Line Tunnel Temperature - High N.A.

f.

RCIC Steam Line Tunnel ATemperature - High N.A.

g.

Drywell Pressure - High N.A.

h.

RCIC Equipment Room a Temperature - High N.A.

5.

RHR SYSTEM STEAM CONDENSING MODE ISOLATION RHR Equipment Area ATemperature - High N.A.

a.

b.

RHR Area Cooler Temperature - High N.A.

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c.

RHR Heat Exchanger Steam Supply Flow High N.A.

LA SALLE'- UNIT 2 3/4 3-18 Amendment No.12

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