ML100630124

Request for Additional Information, Primary Coolant System Pressure Isolation Valves (PIV) Standard Technical Specifications (STS)

ML100630124
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
References
TAC ME2253
Download: ML100630124 (3)

Text

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• • • • i' 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, UNIT NO.1 - LICENSE AMENDMENT REQUEST RE:

REVISIONS TO PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVE REQUIREMENTS CONSISTENT WITH STANDARD TECHNICAL SPECIFICATIONS (TAC NO. ME2253)

Dear Mr. Belcher:

By letter dated September 18, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092640681), as supplemented on October 15, 2009 (ADAMS Accession No. ML092940717), Nine Mile Point Nuclear Station, LLC, submitted for Nuclear Regulatory Commission (NRC) staff review and approval, a license amendment requesting to modify Technical Specification (TS) Sections 3.2.7.1 and 4.2.7.1, "Primary Coolant System Pressure Isolation Valves," to incorporate requirements that are consistent with Section 3.4.5 of the Improved Standard TSs, NUREG-1433, Revision 3.1.

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 February 4,2010, and it was agreed that your response would be provided within 30 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)

REVISION TO PRESSURE ISOLATION VALVE REQUIRMENTS CONSISTENT WITH STANDARD TECHNICAL SPECIFICATIONS LICENSE AMENDMENT REQUEST DOCKET NO. 50-220 The Nuclear Regulatory Commission (NRC) staff is reviewing the Nine Mile Point Nuclear Station, LLC (NMPNS or the licensee) license amendment request dated September 18, 2009, as supplemented on October 15, 2009. The NRC staff has determined that additional information requested below will be needed to support its review.

Provide the specific Surveillance Requirement (SR) frequency intervals for Technical Specification (TS) 3.2.7.1/4.2.7.1 as related to the generic terminology in the applicable American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) and explain how the SR frequency intervals are incorporated into the TSs for NMP1.

TS 4.2.7.1.a is being changed to reference the Inservice Testing (1ST) Program for pressure isolation valve (PIV) test frequency. The fourth interval 1ST Program Plan (Agencywide Documents Access Management System Accession No. ML081900568) states the frequency is per the TSs. Explain how the frequency is determined using the 1ST Program.

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 SUB~IECT: REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.1 - LICENSE AMENDMENT REQUEST RE:

REVISIONS TO PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVE REQUIREMENTS CONSISTENT WITH STANDARD TECHNICAL SPECIFICATIONS (TAC NO. ME2253)

Dear Mr. Belcher:

By letter dated September 18, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092640681), as supplemented on October 15, 2009 (ADAMS Accession No. ML092940717), Nine Mile Point Nuclear Station, LLC, submitted for Nuclear Regulatory Commission (NRC) staff review and approval, a license amendment requesting to modify Technical Specification (TS) Sections 3.2.7.1 and 4.2.7.1, "Primary Coolant System Pressure Isolation Valves," to incorporate requirements that are consistent with Section 3.4.5 of the Improved Standard TSs, NUREG-1433, Revision 3.1.

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 February 4, 2010, and it was agreed that your response would be provided within 30 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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