ML20198J431

Forwards Rev 2 to SIR-97-003, Review of Test Results of Two Surveillance Capsules & Recommendations for Matls Properties & Pressure-Temp Curves to Be Used for Monticello Rpv. Under Separate Cover,Licensee Is Providing LAR to Revise Curves

ML20198J431
Person / Time
Site:	Monticello
Issue date:	12/21/1998
From:	Hammer M NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20198J434	List: ML20198J431 ML20198J445
References
NUDOCS 9812300183
Download: ML20198J431 (2)

Text

Northern states Power Company Monticello Nuclear Generating Plant 2807 West County Road 75 Monticello, MN 55362 1

December 21,1998 10 CFR Pad 50 i Appendix H U S Nuclear Regulatory Commission  ;

Attn: Document Control Desk Washington, DC 20555 '

MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 i Submittal of Report on Reactor Pressure Vessel Specimen Tests Reference 1) Letter from David Musolf, Manager - Nuclear Support Services, Northern i States Power Company, to USNRC Director, Office of Nuclear Reactor  !

Regulation, dated June 5,1984," Final Report of Analysis of Capsule from Reactor Vessel Radiation Surveillance Program" Attached 'or NRC review is a report titled Review of the Test Results of Two Surveillancy Capsules, and Recommendations for the Materials Properties and Pressure-t emperature Curves to be Used for the Monticello Reactor Pressure Vessel,"

prepared by Structural integrity Associates, Inc. dated 5/18/98. This report provides details used for revising Monticello Technical Specification (TS) Reactor Pressure Vessel (RPV) Nil Ductility Transition Pressure-Temperature curves. Under separate cover, NSP is providing a license amendment request to revise these curves. ,

This report is submitted in accordance with 10 CFR 50, Appendix H for the Monticello Nuclear Generating Plant. As noted in the attached report, the Monticello RPV has adequate margins of safety with respect to the end-of-life upper shelf energy and adjusted reference temperature requirements of 10 CFR 50, Appendix G.

This report is based on one of three specimen capsules originally installed prior to plant I startup, and withdrawn in 1981 as the "one fourth ... service life" specimen required by /

Technical Specification 4.6.B.2. One of two sets of specimens in this capsule were tested following removal and the results reported to the NRC per Reference 1. The other half of this specimen set was later reinsteiled in the Prairie Island RPV for Dg

! accelerated irradiation, then removed and tested in 1996. NSP hereby provides this hp .

I report as supplemental information to the 1984 report.

9812300183 981221 ' ~

PDR ADOCK 05000263 a P PDR j 12/21/98 StS JUCENSE\ Tech Specs \RPV Specimen Sutmatal dac

. _ _ . - . _ . . - _ . _ . _ _ . . _ _. . _ . _ . . . __.~.

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l This submittal does not contain any new NRC commitments and does not modify any  ;

prior commitments. Please contact Sam Shirey at (612)-295-1449 if you require further  ;

information related to this request. '

b WH k Michael F. Hammer l

Plant Manager ,

Monticello Nuclear Generating Plant I c: Regional Administrator-Ill, NRC NRR Project Manager, NRC Resident inspector, NRC  ;

State of Minnesota 1 Attn: Kris Sanda I

Attachments Attachment A - Report titled:" Review of the Test Results of Two I Surveillance Capsules, and Recommendations for the Materials l Properties and Pressure-Temperature Curves to be Used for the Monticello Reactor Pressure Vessel," by Structural Integrity Associates, Inc. 5/18/98 i

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