BSEP 10-0098, Response to Request for Additional Information Regarding Request for Alternative Nozzle-to-Vessel Shell Weld and Inner Radius Section Examinations

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Response to Request for Additional Information Regarding Request for Alternative Nozzle-to-Vessel Shell Weld and Inner Radius Section Examinations
ML102360176
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 08/17/2010
From: Mentel P
Progress Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 10-0098, TAC ME3854, TAC ME3855
Download: ML102360176 (3)


Text

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Progress Energy AU6 1,7 2010 SERIAL: BSEP-10-0098 U. SNuclear Regulatory Commission

,.ATTN: Document Control Desk

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Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Response to Request for Additional Information Regarding Request for Alternative to Nozzle-to-Vessel Shell Weld and Inner Radius Section Examinations (NRC TAC Nos. ME3854 and ME3 855)

Reference:

Letter from Phyllis N. Mentel (CP&L) to NRC Document Control Desk, "Request for Alternative to Nozzle-to-Vessel Shell Weld and Inner Radius Section Examinations," dated April 29, 2010, ADAMS Accession Number ML101310390 Ladies and Gentlemen:

By letter dated April 29, 2010, Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., submitted a proposed alternative to the applicable edition of the American Society of Mechanical Engineers (ASME) Code,Section XI, for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. The proposed alternative, which is applicable to the fourth 10-year inservice inspection (ISI) program, would allow reduced requirements for reactor pressure vessel nozzle-to-vessel weld and inner radius examinations. On August 5, 2010, the NRC, via electronic mail, requested additional information regarding the referenced ISI alternative. The enclosure to this letter provides the requested information.

No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Ms. Annette Pope, Supervisor - Licensing/Regulatory Programs, at (910) 457-2184.

Sincerely, Phyllis N. Mentel Manager - Support Services Brunswick Steam Electric Plant Progress Energy Carolinas, Inc.

Brunswick Nuclear Plant PO Box 10429 Southport, NC 28461 V-1

Document Control Desk BSEP 10-0098 Page 2 WRM/wrm

Enclosure:

Response to Request for Additional Information cc (with enclosure):

U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Mr. Philip B. O'Bryan, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 Mr. Jack M. Given, Jr., Bureau Chief North Carolina Department of Labor Boiler Safety Bureau 1101 Mail Service Center Raleigh, NC 27699-1101

BSEP 10-0098 Enclosure Page 1 of 1 Response to Request for Additional Information By letter dated April 29, 2010, Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., submitted a proposed alternative to the applicable edition of the American Society of Mechanical Engineers (ASME) Code,Section XI, for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. The proposed alternative, which is applicable to the fourth 10-year inservice inspection (ISI) program, would allow reduced requirements for reactor pressure vessel nozzle-to-vessel weld and inner radius examinations. On August 5, 2010, the NRC, via electronic mail, requested additional information regarding the referenced ISI alternative. The requested information is provided below.

NRC Question No. 1 Please confirm that previous ultrasonic testing results for the subject welds did not reveal any service-induced indications.

Response No. 1 No service induced flaws have been detected in previous ultrasonic testing of the subject nozzles.

NRC Question No. 2 Please provide the type of weld metal used in the subject welds.

Response No. 2 For each of the subject nozzles, E 8018 NM weld material was used to join the low alloy steel SA533 head and shell material to the A508 carbon steel nozzles. The sealing surfaces of the welds are overlay clad with austenitic stainless steel.

NRC Question No. 3 Please state whether the component (nozzle) identifications listed in Attachment 1 of RR ISI-05 apply to both BSEP units.

Response No. 3 The nozzle configurations listed in Attachment 1 of Relief Request (ISI-05 are applicable to both BSEP units.