ML070510166

RAI Related to License Amendment Request to TS Table 3.3.6.1-1

ML070510166
Person / Time
Site:	LaSalle
Issue date:	02/21/2007
From:	Sands S NRC/NRR/ADRO/DORL/LPLIII-2
To:	Crane C Exelon Generation Co
Sands S,NRR/DORL, 415-3154
References
TAC MD0540, TAC MD0541
Download: ML070510166 (5)

Text

February 21, 2007 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

LASALLE COUNTY STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO TECHNICAL SPECIFICATION TABLE 3.3.6.1-1, PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION (TAC NOS. MD0540 AND MD0541)

Dear Mr. Crane:

By letter to the Nuclear Regulatory Commission (NRC) dated March 16, 2006, Exelon Generation Company, LLC, submitted a request to change Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation, Table 3.3.6.1-1 to revise allowable values for reactor core isolation cooling (RCIC) temperature based leak detection, for the LaSalle County Station, Units 1 and 2.

The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on February 15, 2006, it was agreed that you would provide a response within 45 days from the date of this letter.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3154.

Sincerely,

/RA by M.Marshall for/

Stephen P. Sands, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374

Enclosure:

Request for Additional Information cc w/encl: See next page

Mr. Christopher M. Crane February 21, 2007 President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

LASALLE COUNTY STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO TECHNICAL SPECIFICATION TABLE 3.3.6.1-1, PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION (TAC NOS. MD0540 AND MD0541)

Dear Mr. Crane:

By letter to the Nuclear Regulatory Commission (NRC) dated March 16, 2006, Exelon Generation Company, LLC, submitted a request to change Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation, Table 3.3.6.1-1 to revise allowable values for reactor core isolation cooling (RCIC) temperature based leak detection, for the LaSalle County Station, Units 1 and 2.

The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on February 15, 2006, it was agreed that you would provide a response within 45 days from the date of this letter.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3154.

Sincerely,

/RA by M.Marshall for/

Stephen P. Sands, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374

Enclosure:

Request for Additional Information DISTRIBUTION:

PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNrrPMSSands RidsNrrLAEWhitt RidsAcrsAcnwMailCenter RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr ADAMS Accession Number:ML070510166 NRR-088 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME SSands:mw EWhitt MMarshall DATE 2/21/2007 2/21/2007 2/21/2007 OFFICIAL RECORD COPY

LaSalle County Station, Units 1 and 2 cc:

Site Vice President - LaSalle County Station Robert Cushing, Chief, Public Utilities Division Exelon Generation Company, LLC Illinois Attorney General's Office 2601 North 21st Road 100 W. Randolph Street Marseilles, IL 61341-9757 Chicago, IL 60601 Plant Manager - LaSalle County Station Regional Administrator, Region III Exelon Generation Company, LLC U.S. Nuclear Regulatory Commission 2601 North 21st Road Suite 210 Marseilles, IL 61341-9757 2443 Warrenville Road Lisle, IL 60532-4352 Manager Regulatory Assurance - LaSalle Exelon Generation Company, LLC Illinois Emergency Management 2601 North 21st Road Agency Marseilles, IL 61341-9757 Division of Disaster Assistance &

Preparedness U.S. Nuclear Regulatory Commission 110 East Adams Street LaSalle Resident Inspectors Office Springfield, IL 62701-1109 2605 North 21st Road Marseilles, IL 61341-9756 Document Control Desk - Licensing Exelon Generation Company, LLC Phillip P. Steptoe, Esquire 4300 Winfield Road Sidley and Austin Warrenville, IL 60555 One First National Plaza Chicago, IL 60603 Senior Vice President - Operations Support Exelon Generation Company, LLC Assistant Attorney General 4300 Winfield Road 100 W. Randolph St. Suite 12 Warrenville, IL 60555 Chicago, IL 60601 Director - Licensing and Regulatory Affairs Chairman Exelon Generation Company, LLC LaSalle County Board 4300 Winfield Road 707 Etna Road Warrenville, IL 60555 Ottawa, IL 61350 Vice President - Regulatory Affairs Attorney General Exelon Generation Company, LLC 500 S. Second Street 4300 Winfield Road Springfield, IL 62701 Warrenville, IL 60555 Chairman Associate General Counsel Illinois Commerce Commission Exelon Generation Company, LLC 527 E. Capitol Avenue, Leland Building 4300 Winfield Road Springfield, IL 62706 Warrenville, IL 60555

LaSalle County Station, Units 1 and 2 cc:

Manager Licensing - Braidwood, Byron, and LaSalle Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Vice President - Midwest Operations Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

REQUEST FOR ADDITIONAL INFORMATION LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 In reviewing the Exelon Generation Companys (Exelons) submittal dated March 16, 2006, requesting a change to Technical Specification (TS) 3.3.6.1, Primary Containment Isolation Instrumentation, Table 3.3.6.1-1, to revise allowable values for reactor core isolation cooling (RCIC) temperature based leak detection, for the LaSalle County Station, Units 1 and 2, as shown below:

• Increase the Allowable Value for Function 3.e, RCIC Equipment Room Temperature -

High, from # 291.0 EF to # 297.0 EF

• Decrease the Allowable Value for Function 3.f, RCIC Equipment Room Differential Temperature - High, from # 189.0 EF to # 188.0 EF

• Decrease the Allowable Value for Function 3.g, RCIC Steam Line Tunnel Temperature

- High, from # 277.0 EF to # 267 EF

• Increase the Allowable Value for Function 3.e, RCIC Steam Line Tunnel Differential Temperature - High, from # 155 EF to # 163 EF.

The NRC staff has determined that the following information is needed in order to complete its review:

1. Setpoint calculation methodology: provide documentation (including sample calculations) of the methodology used for establishing the limiting setpoint and the limiting acceptable values for the as-found and as-left setpoints as measured in periodic surveillance testing described below. Indicate the related analytical limits and other limiting design values (and the sources of these values) for each setpoint.

2. Describe the measures to be taken to ensure that the associated instrument channel is capable of performing its specified safety functions in accordance with applicable design requirements and associated analyses. Include in your discussion, information on the controls you employ to ensure that the as-left trip setting after completion of periodic surveillance is consistent with your setpoint methodology. Also, discuss the plant corrective action processes (including any procedures) for restoring channels to operable status when channels are determined to be inoperable or operable but degraded. If the controls are located in a document other than the TS (e.g., plant test procedure), describe how it is ensured that the controls will be implemented.

Enclosure