ML20198K577

Forwards Revised TS Pages (3/4 3-53,3/4 3-53a,6-27 & 6-27a), for Bs,Units 1 & 2.Revised Pages Provides Early Implementation of Rv LI Sys Requirements.Required Procedure Changes & Training Were Completed Prior to Implementation

ML20198K577
Person / Time
Site:	Braidwood
Issue date:	12/23/1998
From:	Tulon T COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20198K578	List: ML20198K577 ML20198K584
References
TAC-M97546, TAC-M97547, TAC-M97548, TAC-M97549, NUDOCS 9812310090
Download: ML20198K577 (2)

Text

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.. Commonwealth IMiv n Company i

liraidwcxxl Generating Station Route al,Ilox Hi Iltacesille, IL 604079619 Tel HI5-45&280I December 23,1998 U.S. Nuclear Regulatory Commission

ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457

Subject:

- Implementation of Reactor Vessel Level Indication System Requirements of improved Technical Specifications (ITS) 3.3.3, " Post Accident Monitoring (PAM)

Instrumentation," and ITS 5.6.7, " Post Accident Monitoring Report."

Reference:

NRC letter, ISSUANCE OF AMENDMENTS (TAC NOS. M97546, M97547, M27548 AND M97549 dated December 22,1998.

Pursuant to 10 CFR 50.4(b), Commonwealth Edison (Comed) Company is submitting the a.tached revised pages (3/4 3-53,3/4 3-53a,6-27, and 6-27a) of the Braidwood Station, Units 1 and 2, Technical Specifications. These revised pages provide an early implementation of the Reactor Vessel Level Indication System requirements of the Braidwood Station, Units 1 and 2, ITS 3.3.3, " Post Accident Monitoring (PAM) Instrumentation," and ITS 5.6.7, " Post

' Accident Monitoring Report." These changes were implemented on December 23,1998. The required procedure changes and training were completed prior to implementation of these changes. The Braidwood Station, Units 1 and 2, ITS were approved in the reference letter on December 22,1998, with the issuance of License Amendment Nos. 98.

Should you have ex ,y questions concerning this letter, please contact Mr. T. W. Simpkin at (815)458-2801 extension 2980.

Respectfully, -

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f Timoth /J. Tulon l Site Vice President Braidwood Station 0}

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Attachment , , i, .*'

fJT48093tst acc cc: Regional Administrator- NRC Region ll1 NRC Senior Resident inspector - Braidwood Station I

9812310090 PDR ADOCK 981223 05000450 Q l P PDR d A Unicom Company

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Attachment I

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Revised Braidwood Station, Units 1 and 2, Technical Specification Pages i

For l> Reactor Vessel Level Indication System

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l Page 3/4 3-53 l Page 3/4 3-53a i

' Page 6-27 Page 6-27a I

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