L-PI-04-060, Revised Page for License Amendment Request Dated 01/30/2004, Application for Technical Specifications Improvement to Eliminate Requirements for Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process

Revised Page for License Amendment Request Dated 01/30/2004, Application for Technical Specifications Improvement to Eliminate Requirements for Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process

ML041340257
Person / Time
Site:	Prairie Island
Issue date:	05/06/2004
From:	Solymossy J Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-PI-04-060
Download: ML041340257 (6)

Text

NMC Committed to Nuclear Excellence Prairie Island Nuclear Generating Plant Operated by Nuclear Management Company, LLC MAY 6 2004 L-PI-04-060 10 CFR 50.90 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Prairie Island Nuclear Generating Plant Units I and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 Revised Page for License Amendment Request (LAR) Dated January 30, 2004, Application For Technical Specification (TS) Improvement To Eliminate Requirements For Hydrogen Recombiners And Hydrogen/Oxygen Monitors Using The Consolidated Line Item Improvement Process By letter dated January 30, 2004, the Nuclear Management Company, LLC (NMC) submitted an LAR titled, "Application For Technical Specification Improvement To Eliminate Requirements For Hydrogen Recombiners And Hydrogen/Oxygen Monitors Using The Consolidated Line Item Improvement Process," which, for the Prairie Island Nuclear Generating Plant, proposed to delete TS requirements related to hydrogen recombiners and hydrogen monitors.

In accordance with discussions with the NRC Staff, this letter provides revised TS page 5.0-40a. License Amendments 162/153, issued on April 28, 2004, revised the number for this page. The TS changes to TS 5.6.8 associated with the subject LAR have been incorporated as shown in Enclosures 1 and 2. The changes are administrative; no substantive changes are proposed.

The information provided in this supplement does not impact the conclusions of the Determination of No Significant Hazards Consideration and Environmental Assessment presented in the original January 30, 2004 submittal.

In accordance with 10 CFR 50.91, NMC is notifying the State of Minnesota of this LAR supplement by transmitting a copy of this letter and attachment to the designated State Official.

Please address any comments or questions regarding this LAR supplement to Mr. Dale Vincent at 1-651-388-1121.

1717 Wakonade Drive East

• Welch, Minnesota 55089-9642 Telephone: 651.388.1121 iA&

Document Control Desk Page 2 Summary of Commitments In this letter NMC has not made any new or revised any Nuclear Regulatory Commission commitments.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on MAY 6 2004

/Josepi . Solymossi e-President, ICirie Island Nuclear Generating Plant Units 1 and 2 Nuclear Management Company, LLC Enclosures (2) cc: Administrator, Region 111, USNRC Project Manager, Prairie Island Nuclear Generating Plant Units 1 and 2, USNRC Senior Resident Inspector, Prairie Island Nuclear Generating Plant Units 1 and 2, USNRC Minnesota Department of Commerce

ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION PAGE (Markup)

Prairie Island Nuclear Generating Plant 5.0-40a Page 1 of 2

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 Steam Generator Tube Inspection Report (continued)

e. If the calculated conditional burst probability based on the projected end-of-cycle (or if not practical, using the actual measured end-of-cycle) voltage distribution exceeds 1E-02, notify the NRC and provide an assessment of the safety significance of the occurrence.

5.6.8 EM Report When a report is required by Condition C or 4 of LCO 3.3.3, "Event Monitoring (EM) -Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

Prairie Island Unit 1 - Amendment No. 4-5814-6 Units 1 and 2 5.0-40a Unit 2 - Amendment No. 449 4-5

ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION PAGE Prairie Island Nuclear Generating Plant 5.0-40a Page 1 of 2

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 Steam Generator Tube Inspection Report (continued)

e. If the calculated conditional burst probability based on the projected end-of-cycle (or if not practical, using the actual measured end-of-cycle) voltage distribution exceeds IE-02, notify the NRC and provide an assessment of the safety significance of the occurrence.

5.6.8 EM Report When a report is required by Condition C or I of LCO 3.3.3, "Event Monitoring (EM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

Prairie Island Unit 1 - Amendment No. 4-5 46Q Units 1 and 2 5.0-40a Unit 2 - Amendment No.4-494-58