ML20206P122
| 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: |
| References | |
| NUDOCS 9901080034 | |
| Download: ML20206P122 (2) | |
Text
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Northern States Power Company
[N Monticello Nuclear Generating Plant
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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
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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 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.
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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 l
also being proposed.
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
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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
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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