ML20036A790

Requests Addl Listed Info Re Generic Ltr 92-01, Reactor Vessel Structural Integrity,10CFR50.54(f)

ML20036A790
Person / Time
Site:	Brunswick
Issue date:	05/07/1993
From:	Milano P Office of Nuclear Reactor Regulation
To:	Richard Anderson CAROLINA POWER & LIGHT CO.
References
GL-92-01, GL-92-1, TAC-M83441, TAC-M83442, NUDOCS 9305140265
Download: ML20036A790 (3)

Text

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May 7, 1993

• Docket Nos. 50-325 and 50-324 Mr. R. A. Anderson Vice President Brunswick Steam Electric Station Carolina Power & Light Company Post Office Box 10429 Southport, North Carolina 28461

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 92-01,

" REACTOR VESSEL STRUCTUP.AL INTEGRITY, 10 CFR 50.54(f)" - BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 (TAC NOS. M83441 AND M83442)

In a letter dated July 6, 1992, Carolina Power & Light Company (CP&L) provided its response to NRC Generic Letter (GL) 92-01, " Reactor Vessel Structural Integrity," Revision 1.

The GL required all licensees to provide information regarding Appendices G and H to 10 CFR Part 50 and the licensees' commitments made in response to GL 88-11, "NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations."

The NRC staff has completed a preliminary review of the information provided in the July 6, 1992, CP&L letter. Based on this review, the staff has determined the need for additional information related to the responses for several of the questions in GL 92-01. Therefore, it is requested that you provide the following information as delineated below.

a. Question 2a in GL 92-01 The CP&L response indicates that the initial upper-shelf energy (USE) values for all beltline materials are not known. A topical report, NED0-32205, "BWR Owners' Group Topical Report on Upper Shelf Energy Equivalent Margin Analysis," was submitted by General Electric Corporation on April 30, 1993, regarding beltline materials with low USE.

Either confirm that this topical report will be used as your licensing bases cr provide your plant-specific approach to demonstrate that all beltline materials that do not have a measured USE will meet the requirements of Appendix G to 10 CFR Part 50.

b. Question 2b in GL 92-01 The CP&L response indicates that chemistry data for plates N16A and N168 are not available.

Provide the values of copper and nickel composition and neutron fluence that were used to determine the increase in nil-ductility transition temperature and the drop in USE for plates N16A and N16B.

Provide the justification for using these values. Describe the methods that were used to determine the copper and nickel chemical compositions.

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i May 7, 1993 l

Mr. R. A. Anderson '

Pursuant to Section 182a of the Atomic Energy Att of 1954, as amended, and 10 CFR 50.54(f), you are requested to submit a *ietter within 60 days of the receipt of th.s letter that provides the information to answer the above questions.

The letter should be addressed to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555, under oath or affirmation. This letter requests information to allow the NRC to complete the review of GL 92-01 to enable the NRC to verify that CP&L is complying with its current licensing basis regarding reactor vessel fracture toughness and material surveillance for the reactor coolant pressure boundary. Accordingly, an evaluation justifying this information request is not necessary under 10 CFR 50.54(f).

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P. L.96-511.

Should you have any questions, please contact me at 301-504-1457.

I Sincerely, ORIGINAL SIGNED BY: B.L. M0ZAFARI FOR:

Patrick D. Milano, Project Manager Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc:

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DISTRIBUTION:

Dosket File?

2 NRC/ Local PDRs PD 11-1 Reading S.A. Varga G.C. Lainas J.A. Mitchell P.D. Anderson P.D. Milano J.

Strosnider 7-D-4 D. Mcdonald I4-B-2 K. Wichman 7-D-4 B. Elliot 7-D-4 S. Sheng 7-D-4 C. Fairbanks 7-D--4 OGC ACRS (10)

E. W. Herschoff, R-II cc:. Plant Service list 0FC LA:PD21:DRPE3 PM:PD21:DRPE C:EMCB AD:PD?l:DRPJs NAME PDAndershb PDM 11a$:tmw JStrosp$her Mhf DATE Oh/F/93 05/.4/93 05/[,h3 05/h/9k Document Name: BRN83441.RAI

Mr. R. A. Anderson Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2 CC:

Mr. Mark S. Calvert Mr. H. A. Cole Associate General Counsel Special Deputy Attorney General Post Brunswick Steam Counsel State of North Carolina Post Office Box 10429 Post Office Box 629 Southport, North Carolina 28461 Raleigh, North Carolina 27602 Mr. Kelly Holden, Chairman Board of Commissioners Mr. Robert P. Gruber Post Office Box 249 Executive Director Southport, NC 28422 Public Staff - NCUC Post Office Box 29520 Resident Inspector Raleigh, North Carolina 27626-0520 U.S. Nuclear Regulatory Commission Star Route 1, PO Box 208 Mr. H. W. Habermeyer, Jr.

Southport, North Carolina 28461 Vice President Nuclear Services Department f;egional Administrator, Region 11 Carolina Power & Light Company U.S. Nuclear Regulatory Commission Post Office Box 1551 - Mail OHS 7 101 Marietta St., N.W., Ste. 2900 Raleigh, North Carolina 27602 Atlanta, Georgia 30323 Mr. Dayne H. Brown, Director Division of Radiation Protection N. C. Department of Environmental, Commerce and Natural Resources Post Office Box 27687 Raleigh, North Carolina 27611-7687 Mr. J. M. Brown Plant Manager - Unit 1 Brunswick Steam Electric Plant Post Office Box 10429 Southport, Norti. Carolina 28461 Public Service Commission State of South Carolina Post Office Drawer 11649 Columbia, South Carolina 29211 Mr. C. C. Warren Plant Manager - Unit 2 Brunswick Steam Electric Plant Post Office Box 10429 Southport, North Carolina 28461

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