ML032330264

Regulatory Commitment Change Summary Report

ML032330264
Person / Time
Site:	LaSalle
Issue date:	08/12/2003
From:	Landahl S Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML032330264 (3)

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Exelon GeneTation Company, LLC www.exeloncorp.com

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Nuclear LaSalle County Station 2601 North 21" Road Marseilles, IL 61341-9757 August 12, 2003 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 LaSalle County Station, Units I and 2 Facility Operating License Nos. NPF-1 1 and NPF-1 8 NRC Docket Nos. 50-373 and 50-374

Subject:

2002 Regulatory Commitment Change Summary Report Enclosed is the Exelon Generation Company (EGC), LLC, commitment change summary for LaSalle County Station for 2002. Revisions to docketed correspondence were processed using the Nuclear Energy Institute's (NEI) 99-04, Revision 0, "Guidelines for Managing NRC Commitment Changes," dated July 1999.

Should you have any questions concerning this letter, please contact Mr. Glen T. Kaegi, Regulatory Assurance Manager, at (815) 415-2800.

Respectfully, Susan R. Landahl Plant Manager LaSalle County Station Attachment cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - LaSalle County Station

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0 Attachment 1 LaSalle County Station Revised Commitment Summary for 2002 Commitment Date of Original Original Commitment Revised Commitment Basis For Revision Revision Commitment Document Tracking No. Revision .

02-01 9/20/02 IE Bulletin 96-03 We shall perform an Inspection of the We shall perform an Inspection of the Current FME practices implemented in response to drywell and wetwell each refueling drywell each refueling outage. We Bulletin 96-03 have been demonstrated to be outage. shall perform an inspection of the effective. By aligning this inspection with the CISI wetwell periodically to coincide with Program, a more efficient utilization of divers would ASME Section Xl. Subsection IWE results ina significant reduction Inpersonnel dose.

containment Inspections.

Detailed inspections of the suppression chamber are performed on a periodic basis (3-4-3 years) as part of the CISI Program, which incorporates the requirements of ASME Section X1, Subsection IWE. Because these inspections are done only during refueling outages (2 year cycle), they are performed every refueling outage except two during the 10 year Interval. The result of this change Isthat during two refueling outages every 10 years, an Inspection of the suppression chamber would not be required.

02-02 8/21/02 Inspection Report The responsibility for the Respirator The commitment has been deleted. Corporate procedure RP-M-440 Incorporates 50-373/80-07 Program shall be vested In one appropriate administrative controls. and references Individual, as specified Inthe Regulatory Reg. Guide 8.15 and NUREG-0041 requirements.

Position of Reg. Guide 8.15 Section 12.1 and NUREG-0041 Section 3.1.5.

02-03 11/5/02 Generic Letter 88-01 Inspections of IGSCC susceptible welds Inspections of IGSCC susceptible The BWRVIP-75 and Risk-Informed Inservice will be done inaccordance with Generic welds will be done Inaccordance with Inspections guidance allows the Inspection of fewer Letter 88-01, 'NRC Position on IGSCC in BWRVIP-75 guidance for normal welds, resulting Inless radiation exposure.

BWR Austenitic Stainless Steel Piping. water chemistry, and Risk-lnfbrmed Inservice Inspections. BWRVIP-75 Is

'BWR Vessel and Internals Project Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules.

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I Attachment LaSalle County Station Revised Commitment Summary for 2002 Commitment Date of Original Original Commitment Revised Commitment Basis For Revision Revision Commitment Document Tracking No. Revision 02-04 1/7/03 NUREG-0519, NUREG-0519 Section 3.9.6 'Inservice The control room position Indication is The change has been evaluated under Safety Evaluation Testing of Pumps and Valves' states that to be removed from the Reactor Core IOCFR50.59 and has been determined to not Report Related to the applicant's proposal to leak test Isolation Cooling (RCIC) System require NRC approval. The change does not the Safe Operation pressure Isolation valves at each periodic Injection Une Inboard Check Valves Increase the probability of accidents or Increase the of LaSalle County test Interval and not each time the valve for Units I and 2. These valves are consequences of accidents or malfunctions of Station Units I and 2 Isdisturbed for those systems which are pressure isolation valves. equipment already analyzed, or Introduce new rated at a lower pressure than the failure modes or accidents. The position IndIcatIon reactor coolant system Isacceptable for These valves have position Indication Isnot required by the plant's Technical the following reasons: (1)full closure of that does not always reset to Indicate Specifications.

these valves Isverified Inthe control that the valve closed after It has been room by direct monitoring position opened. Experience has shown that Indicators, the cam that operates the valve limits switch will not always rotate to the dosed position after the disc Isseated due to problems Inthe design.

The Inboard position Indication is being removed because the unreliable indication can cause operational challenges and require drywell entries causing unnecessary personnel dose.

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