ML20206P122

Forwards LAR for License DPR-22,revising TS pressure-temp Curves Contained in Figures 3.6.1,3.6.2,3.6.3 & 3.6.4, Deleting Completed RPV Sample SRs & Requirement to Withdraw Specimen at Next Refueling Outage & Removing Redundant SR

ML20206P122
Person / Time
Site:	Monticello
Issue date:	12/31/1998
From:	Hammer M NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20206P125	List: ML20206P122 ML20206P127 ML20206P133
References
NUDOCS 9901080034
Download: ML20206P122 (2)

Text

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Northern States Power Company

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Monticello Nuclear Generating Plant 2807 West County Road 75 Monticello, MN 55362 i

December 31,1998 10 CFR 50 Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 l MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 l

l License Amendment Request Dated December 31,1998 Revision of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Removal of Standby Liquid Control Relief Valve Setpoint Attached is a request for a change in the Technical Specifications, Appendix A of the l Operating License for the Monticello Nuclear Generating Plant. This request is submitted in l accordance with the provisions of 10 CFR Part 50, Section 50.90.

The purpose of this License Amendment Request is to revise the Technical Specification (TS) pressure-temperature (P-T) limit curves, Figures 3.6.1,3.6.2,3.6.3, and 3.6.4. The revised curves were generated based upon an evaluation of all Monticello Reactor Pressure Vessel (RPV) materials using a new Monticello plant specific chemistry factor.

The changes are based on the results of the Charpy V-Notch impact tests of two sets of

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surveillance specimens containing limiting materials from the Monticello reactor pressure vessel beltline region. A report providing the information reauired by 10 CFR Part 50, Appendix H, and supporting these changes was submitted for NRC Staff review on f December 21,1998. /

Associated Limiting Conditions for Operation (LCO), Surveillance Requirements (SR), and Bases sections have been updated. Deletion of completed RPV sample surveillance l requirements and the requirement to withdraw a specimen at the next refueling outage are also being proposed.

l This request also proposes to remove a redundant setpoint surveillance requirement for the Standby Liquid Control System relief valves.

Exhibit A contains a description of the proposed changes, the reasons for requesting the changes, a Safety Evaluation, a Detgrmination of No Significant Hazards Consideration, uge 9901000034 901231 PDR. ADOcK 05000263 P PDR a

USNRC NORTHERN STATES POWER COMPANY December 31,1998 Page 2 and an Environmental Assessment. Exhibit B contains the current Technical Specificahon pages marked up with the proposed changes. Exhibit C contains revised Monticello Technical Specification pages. '

This submittal does not contain any new NRC commitments and does not modify any prior ,

commitments. This submittal fulfills NSP's September 17,1998 commitment to update the [

Monticello RPV P-T curves by December 31,1998. Please contact Sam Shirey at (612)-

295-1449 if you require further information related to this request. .

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Michael F. Hammer Plant Manager Monticello Nuclear Generating Plant c: Regional Administrator-Ill, NRC NRR Project Manager, NRC Resident Inspector, NRC State of Minnesota Attn: Kris Sanda Attachments: Affidavit to the US Nuclear Regulatory Commission Exhibit A - Evaluation of Proposed Changes to the Technical Specifications for Operating License DPR-22 Exhibit B - Proposed Changes Marked Up on Existing Technical Specification Pages Exhibit C - Revised Monticello Technical Specification Pages I

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