BSEP-94-0316, Forwards Reactor Vessel Matl Surveillance Specimen Test Results,Per 10CFR50,App H

Forwards Reactor Vessel Matl Surveillance Specimen Test Results,Per 10CFR50,App H

ML20072F242
Person / Time
Site:	Brunswick
Issue date:	08/17/1994
From:	Lopriore R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20072F244	List: BSEP-94-0316, Forwards Reactor Vessel Matl Surveillance Specimen Test Results,Per 10CFR50,App H ML20072F250 ML20072F261 ML20072F266 ML20072F271 ML20072F286 ML20072F290
References
BSEP-94-0316, BSEP-94-316, NUDOCS 9408230258
Download: ML20072F242 (6)

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4 CP&L Carolina Power & Light Company PO Box 10429 Southport NC 28461 August 17,1994 SERIAL: BSEP 94-0316 10 CFR 50 APPENDIX H U. S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS 1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 SUBMITTAL OF REACTOR VESSEL MATERIAL SURVEILLANCE SPECIMEN TEST RESULTS FOR BRUNSWICK UNIT 1 Gentlemen:

The purpose of this letter is to provide the NRC staff,in accordance with 10 CFR 50, Appendix H, reactor vessel material surveillance specimen test results for Carolina Power & Light Company's (CP&L) Brunswick Steam Electric Plant, Unit 1.

CP&L removed the first raactor vessel surveillance capsule for Brunswick Unit 1 on August 17,1993. The enclosed report (Enclosure 2) summarizes the mechanical testing and fluence analysis associated with this capsule. The report includes the data required by ASTM E 185, as specified in Paragraph II.B.1 of 10 CFR 50, Appendix H, and the results of all fracture toughness testa conducted on the beltline materials in the irradiated and  ;

l unitradiated conditions. As noted in the report, no changes in the Brunswick Technical Specification pressure-temperature limit curves or operating limits are required as a result of these analyses.

The attached report also updates end-of-license fluence and mechanical properties )

projections for the reactor vessel beltline materials based on the results of the survei!!ance 1 capsule testing. By letter dated May 13,1994, CP&L committed to evaluate the impact of l the BWR Owners' Group methodology for determining initial RTnm values for beltline ,

materials and provide the results of that assessment along with the surveillance capsule l test results. This date was provided based on anticipated NRC staff approval of the  !

BWROG methodology. To date, the revised BWROG methodology has not been finalized and submitted to the NRC staff for approval; therefore, CP&L will complete the assessment and provide the results to the NRC staff following NRC staff approval of the finalized BWROG Topical Report.

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BSEP 94-0316 / Page 2 In the May 13,1994 letter, CP&L also committed to revise the GE NEDO reports i describing the reactor vessel material surveillance programs for Brunswick Units 1 and 2. l These revisions corrected the information of the reactor vessel materials that had been i reversed in the earlier NEDO reports (reference Brunswick Licensee Event Report 1-94-005 I and 1-94-005 Supplement 1). Enclosed for your information are copies of revised NEDO documents, NEDO-24161, Revision 1, for Brunswick Unit 1 and NEDO-24157, Revision 2,

1. or Brunswick Unit 2 (Enclosures 3 and 4).

Please refer any questions regarding this submittal to Mr. M. A. Turkal at (910) 457-3066.

I Sincerely, I

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R. P. Lopriore l Manager - Regulatory Affairs  ;

Brunswick Nuclear Plant KAH/

Enclosures cc: Mr. S. D. Ebneter, Regional Administrator, Region ll  ;

Mr. P. D. Milano, NRR Senior Project Manager - Brunswick Units 1 and 2  !

Mr. C. A. Patterson, Brunswick NRC Senior Resident inspector The Honorable H. Wells, Chairman - North Carolina Utilities Commission I

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l ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62 l

LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by Carolina Power & Licht Company in this document. Any other actions discussed in the submittal represent r intended or planned actions by Carolina Power & Light Company. They are described to  ;

the NRC for the NRC's information and are not regulatory commitments. Please notify the Manager-Regulatory Affairs at the Brunswick Nuclear Plant of any questions regarding this document or any associated regulatory commitments.

Committed Commitment date or outage

1. CP&L will evaluate the impact of the BWR Owners' Group N/A methodology for determining initial RTno, values for beltline materials and provide the results to the NRC staff following NRC staff approval of the finalized BWROG Topical Report.

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1 ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 & 50-324 I

OPERATING LICENSES DPR-71 & DPR-62 BRUNSWlCK STEAM ELECTRIC PLANT UNIT 1 REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAM

SUMMARY

REPORT SR-BNP1-1005-OO1 FIRST CAPSULE REMOVAL TEST RESULTS AND PROJECTIONS AUGUST 1994 E2-1

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ENCLOSURE 3 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62 NEDO-24161, Rev.1 INFORMATION ON REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM BRUNSWICK STEAM ELECTRIC PLANT - UNIT 1 1

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ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62 NEDO-24157, Rev. 2 INFORMATION ON REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM BRUNSWICK STEAM ELECTRIC PLANT - UNIT 2 E4-1

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