ML20106A510

Responds to 920901 Generic Ltr 89-01, Implementation of Programmatic of Controls for RETS in Administrative Controls Sections of TS & Relocation of Procedural Details of RETS to ODCM or Pcp. Applicable TS Encl

ML20106A510
Person / Time
Site:	LaSalle
Issue date:	09/18/1992
From:	Shields J COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20106A513	List: ML20106A510 ML20106A569
References
GL-89-01, GL-89-1, NUDOCS 9209280133
Download: ML20106A510 (2)

Text

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- Commonwealth Edison

,~- 1400 Opus Place Vl Downers Grove, Cunois 00515 September 18, 1992 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ,

Attn: Document Control Desk

Subject:

LaSalle County Station Units 1 and 2 Ce re: tion to Technical Specification Surveillance Requirement 4.11.2.2.1 Generic letter 89-01 Approved Changes NRCllochetJosm30_313_andJ0-314

References:

(a) P.L. Piet letter to USNRC dated May 22, 1991; Application for Amendment to facility Operating Licenses NPF-11 and NPF-18, Appendix A. Technical Specifications, Generic Letter 89-01 (b) B.L. Siegel letter to T.J. Kovach dated September 1, 1992;

Issuance of Amendments

Dear Dr. Murley,

In the reference (a) submittal,-Commonwealth Edison (CECO) requested Amendment to the LaSalle County Station Technical. Specifications to incorporate the guidance provided in Generic Letter 89-01, " Implementation of-i Programmatic Controls for Radlological Effluent Technical Specifications (RETS) in the Administrative Controls Section of the Technical Specifications and Relocation of Procedural Details of RETS to Offsite Dose Calculation Manual (ODCH) or Process Control Program (PCP)." lu response, the NRC issued the reference (b) Safety Evaluation Report (SER) and changed Technical Specification pages.

During CECO's-review of the SER, a correction to the Main Condenser.

' Surveillance Requirement 4.11.2,2.1 for each Unit was noted. The amendment relocated the noble gas release information contained in Specification 3.3.7.ll,--then called Radioactive Gaseous Effluent Monitoring Instrumentation, revised tc be called Explosive Gas Monitoring Instrumentation, to the ODCM. However. Main. Condenser Surveillance .

Requirement 4.11.2.2.1 still referred to Specification 3.3.7.11.for noble gas-monitoring. This Surveillance Requirement should have referenced the ODCM.

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Dr. T.E. Murley September 18. 1992 l 1

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CECO proposes that Surveillance Requirement 4.11.2.2.1 be corrected to  ;

reid as follows:

The rhdloactivity rate of noble gases prior to the holdup line shall be  !

continuously monitored in accordance with the_0DCM. l A copy of the corrected Technical Specification pages is attached. This change does not change the intent of the original amendment request, as it corrects a reference Specification which changed as a part of relocating i sections in the original request.

Please direct any questions to this office.

Respectfully, 't

.l

{r Y l JoAnn Shields Nuclear Licensing Administrator i

Attachment l

I cc: A. Bert Davis, Regional Administratcw - RIII l 0.L. Sitgel, Project Manager - NRR i D.L. Hills, Senior Resident Inspector - 1.SCS  ;

! Office of Nuclear Safety - IDNS I

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