ML100630125

Request for Additional Information RR-ISI-25

ML100630125
Person / Time
Site:	Nine Mile Point
Issue date:	03/18/2010
From:	Richard Guzman Plant Licensing Branch 1
To:	Belcher S Nine Mile Point
Guzman R, NRR/DORL, 415-1030
References
TAC ME2812
Download: ML100630125 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March ta, zoio Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 SUB~IECT: REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.1 (NMP1) - RELIEF REQUEST RR-ISI-25 (TAC NO. ME2812)

Dear Mr. Belcher:

By letter dated Novermber 24, 2009 (Agencywide Documents Access Management System (ADAMS) Accession No. ML093350523) , Nine Mile Point Nuclear Station, LLC, submitted for Nuclear Regulatory Commission (NRC) staff review and approval, RR-ISI-25 for the third 1a-year inservice inspection (lSI) interval for NMP1 requesting relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI.

The NRC staff is reviewing the information provided in that letter and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on March 5, 2010, and it was agreed that your response would be provided within 45 days from the date of this letter.

Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220

Enclosure:

As stated cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION (RAI)

NINE MILE POINT NUCLEAR STATION, LLC NINE MILE POINT, UNIT NO.1 (NMP1)

REQUEST FOR RELIEF RR-ISI-25 RELATED TO RISK-INFORMED PIPING EXAMINATIONS DOCKET NO. 50-220 The Nuclear Regulatory Commission (NRC) staff is reviewing the Nine Mile Point Nuclear Station, LLC (NIVIPNS or the licensee) submittal dated November 24,2009. The submittal requested relief from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirements. The request pertains to the use of an alternative to the risk-informed piping examinations for the third 1O-year inservice inspection interval for NMP1. The NRC staff has determined that additional information requested below will be needed to support its review.

1. Please provide the piping and weld material for each component listed in Table 1 of the relief request submittal.

2. Please explain how you calculated 62.5% weld coverage for components 32-WD-002 and 32-WD-045.

3. Under "Risk Category 4 Welds," you state that "surface conditioning may have improved the ability to scan over the weld; however, Code coverage would not have increased because of Title 10 of the Code of Federal Regulations 50.55a(b)(xv)(A)(2) requirements ... therefore, surface conditioning was not performed." Figures 5 and 6 for components 32-WD-002 and 32-WD-045, respectively, indicate that the welds are accessible for examination from both sides. In light of this, please clarify why surface conditioning to improve the surface profile due to radial shrinkage would not have increased Code coverage.

Enclosure

March 18, 2010 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UI\IIT NO.1 (I\IMP1) - RELIEF REQUEST RR-ISI-25 (TAC NO. ME2812)

Dear Mr. Belcher:

By letter dated Novermber 24, 2009 (Agencywide Documents Access Management System (ADAMS) Accession No. ML093350523) , Nine Mile Point Nuclear Station, LLC, submitted for Nuclear Regulatory Commission (NRC) staff review and approval, RR-ISI-25 for the third 1a-year inservice inspection (lSI) interval for NMP1 requesting relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI.

The NRC staff is reviewing the information provided in that letter and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on March 5, 2010, and it was agreed that your response would be provided within 45 days from the date of this letter.

Sincerely, IRA!

Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220

Enclosure:

As stated cc w/encl: Distribution via Listserv DISTRIBUTION:

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