CNRO-2002-00054, Proposed Alternative to ASME Examination Requirements for Repairs Performed on Reactor Vessel Head Penetrations

Proposed Alternative to ASME Examination Requirements for Repairs Performed on Reactor Vessel Head Penetrations

ML040440450
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/26/2002
From:	Krupa M Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNRO-2002-00054
Download: ML040440450 (2)

Text

i;*

ii Entergy Operations, Inc.

1340 Echelon Parkway Jackson. MS 39213-8298 Tel 601 368 5758 Michael A. Krupa Director NuclearSafety& Ucenming CNRO-2002-00054 November 26, 2002 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Entergy Operations, Inc.

Proposed Alternative to ASME Examination Requirements for Repairs Performed on Reactor Vessel Head Penetrations Arkansas Nuclear One, Unit I Docket No. 50-313 License No. DPR-51

REFERENCE:

Entergy Operations, Inc. Letter No. CNRO-2002-00052 to the NRC,

'Proposed Alternative to ASME Examination Requirements for Repairs Performed on Reactor Vessel Head Penetrations,* dated October 28, 2002

Dear Sir or Madam:

In the referenced letter, Entergy Operations, Inc. (Entergy) proposed alternatives to the requirements of ASME Sections III and Xl as applied to reactor pressure vessel (RPV) nozzles. These alternatives were presented in Relief Request Nos. ANO1-R&R-003, Rev. 0 and ANO1-R&R-004, Rev. 0, respectively, and apply to Arkansas Nuclear One, Unit I (ANO-1).

In a telephone call between NRC staff representatives and Entergy representatives held on November 6, 2002, the staff verbally authorized the use of ANO1-R&R-003 and -004. In addition, the staff asked Entergy to transmit copies of three evaluations being performed to support the repairs as discussed in ANO1-R&R-004. These evaluations were described in ANO1-R&R-004 as follows:

1) Flaw evaluations for a postulated radial comer crack on the uphill side of the reactor head penetration ANO Calculation 86-E-0074-156 (Framatome Document 32-5021538-00)]

2) Evaluation to determine the potential for debris from a cracking J-groove partial penetration weld [ANO Calculation 86-E-0074-164 (Framatome Document 51-5012789-00)]

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3) A limit load analysis considering the ductile Alloy 6001alloy 690 materials along the designated flaw propagation path [ANO Calculations 86-E-0074-160 and 86-E-0074-161 (Framatome Documents 51-5012728-03 and 32-5021539-00)]

The evaluations have been completed by Framatome-ANP and approved by Entergy for use at ANO-1. They are contained in Enclosures 1, 2, and 3, respectively.

Framatome-ANP considers information contained In ANO Calculations 86-E-0074-156 and 86-E-0074-161 (Framatome Documents 32-5021538-00 and 32-5021539-00) to be proprietary and confidential pursuant to 10 CFR 2.790(a)(4) and 10 CFR 9.17(a)(4). As such, Framatome-ANP has requested that this Information be withheld from public disclosure. The affidavit supporting this request is -provided in Enclosure 4. Entergy will provide nonproprietary versions of these calculations under separate letter as they become available.

Should you have any questions regarding this letter, please contact Guy Davant at (601) 368-5756.

This letter contains no commitments.

Very truly yours,

.i-..: .. : . ..

MAK/GHD/bal

Enclosures:

1. ANO Calculation 86-E-0074-156

2. ANO Calculation 86-E-0074-164

3. ANO Calculations 86-E-0074-160 and 86-E-0074-161

4. Affidavit for Withholding Information from Public Disclosure cc: Mr. C. G. Anderson (ANO)

Mr. W. R. Campbell (ECH)

Mr. G. A. Williams (ECH)

'i Mr. T. W. Alexion, NRR Project Manager (ANO-2)

Mr. R. L. Bywater, NRC Senior Resident Inspector (ANO)

Mr. E. W. Merschoff, NRC Region IV Regional Administrator Mr. W. D. Reckley, NRR Project Manager (ANO-1)