ML20078Q288

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Amend 86 to License NPF-18,adding Footnote to TS Table 4.3.1.1-1 to Allow one-time Extension of Surveillance Interval for MSIV Closure Reactor Protection Sys Channel Functional Test
ML20078Q288
Person / Time
Site: LaSalle 
Issue date: 02/14/1995
From: William Reckley
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20078Q289 List:
References
NUDOCS 9502210189
Download: ML20078Q288 (4)


Text

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+4 UNITED STATES j

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3000HM01

.....,o COMMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LASALLE COUNTY STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 License No. NPF-18 1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment filed by the Commonwealth Edison Company (the licensee) dated January 30, 1995, complies 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 conformity with the application, the provisions of the Act, and the regulations of the Commission; C.

There is reasonable 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; 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 enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follows:

9502210189 950214 DR ADOCK O 34

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 86, and the Environmental Protection 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.

l 3.

This amendment is effective upon date of issuance and shall be implemented prior to 2:45 a.m. CST on February 15, 1995.

FOR THE NUCLEAR REGULATORY COMMISSION William D. Reckley, Proj Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Jesuance: February 14, 1995 t

6

a.

ATTACHMENT TO LICENSE AMENDMENT NO. 86 FACILITY OPERATING LICENSE NO. NPF-18 DOCKET NO. 50-374 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains a vertical line indicating the area of change.

REMOVE INSERT 3/4 3-7 3/4 3-7 t

f i

I A

b Y

1

?.

~

(

5 TABLE 4.3.1.1-1

~

m REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE RE0UIREMENTS l

CHANNEL OPERATIONAL c

CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH FUNCTIONAL UNIT

_CtlECK TEST CALIBRATION SURVEILLANCE REOUIRED N

s m

1.

Intermediate Range Monitors N

a.

Neutron Flux - High S/U

,S S/UM,W R

2 5

W R

3,4,5 b.

Inoperative NA W

NA 2,3,4,5 2.

Average Power Range Monitor:"1 a.

Neutron Flux - High, Setdown S/Uch),5 S/UM, W SA 1, 2 S

W SA 3, 5 R

b.

Flow Biased Simulated Thermal Power-Upscale S, D*

S/U

,W W(d) M, SA, R

  • 1 W

Y c.

Fixed Neutron Flux -

High S

S/UM, W W#, SA t

d.

Inoperative NA W

NA 1, 2, 3, 5 3.

Reactor Vessel Steam Dome Pressure - High NA M

Q 1, 2 4.

Reactor Vessel Water Level -

Low, level 3 NA M

R 1, 2 5.

Main Steam Line Isolation Valve - Closure NA Q#

R 1

3E 6.

Main Steam Line Radiation -

G High S

M R

1, 2 32 7.

Primary Containment Pressure -

High NA M

Q 1, 2

.E E

  1. The quarterly surveillance interval which began at 03:45 a.m. CDT October 23, 1994, is extended until the scheduled shutdown ending Unit 2 operating cycle 6.

The total surveillance interval shall not exceed 120 days, i.e., the surveillance shall be performed prior to 02:45 a.m. CST on February 20, 1995.

.