ML12181A009

Correction to Relief from the Requirements of the ASME Code, Relief Request No. PR-01 for Fifth Inservice Testing Interval

ML12181A009
Person / Time
Site:	Oyster Creek
Issue date:	07/03/2012
From:	John Lamb Plant Licensing Branch 1
To:	Pacilio M Exelon Nuclear
Lamb J
References
TAC ME7616
Download: ML12181A009 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 3,2012 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

OYSTER CREEK NUCLEAR GENERATING STATION-CORRECTION TO RELIEF FROM THE REQUIREMENTS OF THE ASME CODE, RELIEF REQUEST NO. PR-01 FOR FIFTH INSERVICE TESTING INTERVAL (TAC NO. ME7616)

Dear Mr. Pacilio:

By letter dated November 17, 2011 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML113250626), Exelon Nuclear submitted Relief Request (RR) PR-01 for Oyster Creek Nuclear Generating Station (OCNGS) during the fifth Inservice Testing (1ST) interval, requesting the use of an alternative to certain requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code).

By letter dated June 21, 2012 (ADAMS Accession No. ML120050329), the U.S. Nuclear Regulatory Commission (NRC) staff authorized the alternative described in RR PR-01 for the fifth 1ST interval at OCNGS, which will begin on October 14,2012, and ends on October 13, 2022.

Subsequently, it was discovered that the NRC staff made a typographical error in the third sentence of the second paragraph on page 5 of the safety evaluation (SE). The sentence currently reads:

However, the NRC staff has reviewed OMN-18, and currently has no concerns with its usage, providing that the high values of the Group A test "Required Action Range" for flow (Q) and differential pressure (~P) are greater than 106%

of the respective reference values.

The sentence should be corrected in the SE to read the following:

However, the NRC staff has reviewed OMN-18, and currently has no concerns with its usage, providing that the high values of the Group A test "Required Action Range" for flow (Q) and differential pressure (~P) are less than 106% of the respective reference values.

M. Pacilio -2 If you have any questions regarding this matter, please contact me at (301) 415-3100 or bye-mail at John.Lamb@nrc.gov.

Sincerety,

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JO~nl.:!:'b~ s7nior Project Man~er PlanVLicensing Branch 1-2 Divi¢ion of Operating Reactor Licensing Office of Nuclear Reactor Regulation

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Docket No. 50-219 cc: Distribution via Listserv

If you have any questions regarding this matter, please contact me at (301) 415-3100 or bye-mail at John.Lamb@nrc.gov.

Sincerely,

/raj John G. Lamb, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-219 cc: Distribution via Listserv DISTRIBUTIONPUBLIC RidsNrrDorlLpl1-2 RidsNrrPMOysterCreek RidsNrrLAABaxter RidsNrrDeEptb RidsRgn1 MailCenter RidsOgcRp RidsAcrsAcnw_MailCTR JHuang, NRR LChang OEDO LPL 1-2 RIF ADAMS Accession No.: ML12181A009 OFFICE LPL 1-2/PM LPL 1-2/LA LPL 1-2/BC NAME JLamb ABaxter MKhanna "

DATE 07102/12 07102112 07103/12 OFFICIAL RECORD COpy