ML092720231

Correction Letter for License Amendment Nos. 195 and 182, Revise Local Power Range Monitor Calibration Frequency

ML092720231
Person / Time
Site:	LaSalle
Issue date:	10/02/2009
From:	Goodwin C Plant Licensing Branch III
To:	Pardee C Exelon Nuclear
Goodwin, Cameron S, NRR/DORL, 415-3719
References
TAC MD9414, TAC MD9415
Download: ML092720231 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 2, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

LASALLE COUNTY STATION, UNITS 1 AND 2 - CORRECTION LETTER FOR LICENSE AMENDMENT NOS. 195 AND 182, RE: REVISE LOCAL POWER RANGE MONITOR CALIBRATION FREQUENCY (TAC NOS. MD9414 AND MD9415)

Dear Mr. Pardee:

By letter dated September 16, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092440755), the Nuclear Regulatory Commission (NRC) staff issued Amendment Nos. 195 and 182 to Facility Operating License Nos. NPF-11 and NPF-18 for the LaSalle County Station, Units 1 and 2, respectively. The amendments are in response to your application dated July 25,2008 (ADAMS Accession No. ML082110187), as supplemented by letters dated October 31, 2008 (ADAMS Accession No. ML083080059), February 17, 2009 (ADAMS Accession No. ML090480372), May 8,2009 (ADAMS Accession No. ML092380433) and July 27,2009 (ADAMS Accession No. ML092100162).

An administrative error was identified in the amendments. On Technical Specification (TS) page 3.3.1.3-3, Surveillance Requirement (SR) 3.3.1.3.5 should state U< 60% of rated recirculation drive flow." This SR was not part of the changes for this amendment request.

Please replace TS page 3.3.1.3-3 with the enclosed copy.

The incorrect information was editorial in nature. The corrections do not change the approval conveyed by the amendments, or the conclusions reached by the associated safety evaluation.

We regret any inconvenience this may have caused you.

Sincerely, Cameron S. Goodwin, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374

Enclosure:

Technical Specification page 3.3.1.3-3 cc w/encl: Distribution via ListServ

OPRM Instrumentation 3.3.1.3 SURVEILLANCE REQUIREMENTS

- - - - - - - - - - - - . - - - . - - - . - - - . - - - - - - - . - - .. NOT E- . - - - - - - - - - - - . - - - - - - - - - . - . - . - - - - - - - -

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the OPRM maintains trip capability.

SURVEI LLANCE FREQUENCY SR 3.3.1.3.1 Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.1.3.2 Cal i brate the 1 oca 1 power range monitors. 2000 effective full power hours SR 3.3.1.3.3 - - - - - - - - - - - - - - - . - - NOT E- - - - - - - - - - - - - - - - - - - -

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. The setpoints 24 months for the trip function sha 11 be as specified in the COLR.

SR 3.3.1.3.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SR 3.3.1.3.5 Verify OPRM is not bypassed when THERMAL 24 months POWER is ~ 28.6% RTP and recirculation drive flow is < 60% of rated recirculation drive flow.

SR 3.3.1.3.6 - - - - - - - -. - - - - - - - - - - NOTE - - _. - - - - - - - - - - - -

Neutron detectors are excluded.

Veri fy the RPS RESPONSE TIME is within 24 months on a limits. STAGGERED TEST BASIS LaSalle 1 and 2 3.3.1.3-3 Amendment No. 195/182

ML082110187), as supplemented by letters dated October 31,2008 (ADAMS Accession No. ML083080059), February 17, 2009 (ADAMS Accession No. ML090480372), May 8,2009 (ADAMS Accession No. ML092380433) and July 27,2009 (ADAMS Accession No. ML092100162).

An administrative error was identified in the amendments. On Technical Specification (TS) page 3.3.1.3-3, Surveillance Requirement (SR) 3.3.1.3.5 should state "< 60% of rated recirculation drive flow." This SR was not part of the changes for this amendment request.

Please replace TS page 3.3.1.3-3 with the enclosed copy.

The incorrect information was editorial in nature. The corrections do not change the approval conveyed by the amendments, or the conclusions reached by the associated safety evaluation.

We regret any inconvenience this may have caused you.

Sincerely, IRA!

Cameron S. Goodwin, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374

Enclosure:

Technical Specification page 3.3.1.3-3 cc w/encl: Distribution via ListServ DISTRIBUTION:

PUBLIC LPL3-2 RtF RidsNrrPMLaSalie Resource RidsOgcRp Resource RidsNrrDirsltsb Resource RidsRgn3MailCenter Resource RidsNrrDorlLpl3-2 Resource RidsNrrLATHarris Resource RidsNrrDoriDpr Resource RidsAcrsAcnw_ MailCTR Resource ADAMS Accession No ML092720231 NRR-106 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME CGoodwin THarris SCampbell DATE 10/2/09 10/2/09 10/2/09