ML20217D172

Forwards RAI Re 990729 Request for Amend to TSs Allowing Special SG Insp for Plant,Unit 2.Questions Re Proposed Insp Scope for Axial Cracking Degradation in Eggcrate Support Region Submitted.Response Requested by 991015

ML20217D172
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/08/1999
From:	Nolan M NRC (Affiliation Not Assigned)
To:	Hutchinson C ENTERGY OPERATIONS, INC.
References
TAC-MA6224, NUDOCS 9910150033
Download: ML20217D172 (5)

Text

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' UNITED STATES 4

j NUCLEAR REGULATCRY COMMISSION g

WASHINGTON, D.C. 3056HmM October 8, 1999 Mr. C. Randy Hutchinson Vice President, Operations ANO Entergy Operations, Inc.

1448 S. R. 333 Russellville, AR 72801

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED TECHNICAL SPECIFICATION CHANGES FOR A SPECIAL STEAM GENERATOR INSPECTION - ARKANSAS NUCLEAR ONE, UNIT NO. 2 (TAC NO. MA6224)

Dear Mr. H_ tchkison:

During the review of your request for an amendment to the Technical Specifications allowing a

- special steam generator inspection for Arkansas Nuclear One, Unit No. 2, dated July 29,1999 (2CAN079903), we identified several areas of your submittal that required further clarification.

The following is a list of questions regarding your proposed inspection scope for axial cracking

' degrada3on in the eggerate support region.

1.

Please provide information from past inspections that demonstrate how the size of the

' indications varies with eggerate support. Something similar to Figure 1 of the August 6, 1999 (2CAN089901), submittal would be appropriate. However; this information should be provided in terms of indication size rather than just number of indications.

. 2.

Confirm your plans to in-situ pressure test tubes that meet the Electric Power Research Institute guidelines if the indications in the tubes have not been bounded by previous test results.

The following is a list of questions regarding your proposed inspection scope for the top-of-tubesheet circumferential cracking degradation mechanism.

~ 1.

Provide information that demonstrates that the size of newly identified circumferential

. Indications has decreased over the past operating cycles. You provided information on the number of these indications decreasing over the past inspections in Figure 2 of the August 6,1999, submittal.- in addition, include a discussion of the inspection techniques utilized in this area since 1992 to fully characterize the information provided regarding crack number and s'a.

2. : Please' provide a basis for your selection criteria for tube inspection if results from the "A" steam generator indicate that the "B" steam generator must be inspected.

3. : Consider expanding the inspection scope to ensure a two-tube buffer exists around any

, tube that meets the in-situ pressure test criteria, regardless of whether the tube is tested or

'.not. This would suppon the logic that the inspection area is comprised of the most limiting tubes.

NRC RtF CENTER CDPtPDI) 9910150033 991008 7

PDR ADOCK 05000368

.t-G PDR --

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,- w C. R. Hutchinson "

' The following question pertains to your proposed' inspection scope for both axial cracking degradation.in the eggcrate support region and top-of-tubesheet circumferential cracking degradation.

. Confirm ycur plan to perform condition monitoring and an operational assessment based on the mid-cycle inspection findings and that the results from these efforts will be included

.in a report submitted to the NRC.

The need to' provide complete justification to support the requested changes and the agreement of the ANO staff to comply with this request was discussed with members of your staff during a I

telephone call on September 15,1999. Based on that telephone call, our understanding is that the information can be supplied within a few weeks. A mutually agreed upon due date of

~

October 15i 1999, was established with Mr. Steve Bennett of your staff.

Sincerely, h.

M. Christopher Nolan, Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No'. 50-368

' cc: See next page g

a-

Arkansas Nuclear One l'

cc:

l Executive Vice President Vice President, Operations Support

& Chief Operating Officer Entergy Operations, Inc.

Entergy Operations, Inc.

P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 l

Jackson, MS 39286-1995 l

Wise, Carter, Child & Caraway l-Director, Division of Radiation P. O. Box 651 l

Control and Emergency Management Jackson, MS 39205 Arkansas Department of Health 4815 West Markham. Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.

Washington, DC 20005-3502 Manager, Rockville Nuclear Licensing i

Framatone Technologies 1700 Rockville Pike, Suite 525 Rockville, MD 20852 Senior Resident inspector U.S. Nuclear Regulatory Commission P. O. Box 310 i

London, AR 72847 l

Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope County Courthouse Russellville, AR 72801 ~

May 1999 l

L

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i October 8, 1999 l

C. R. Hutchinson The following question pertains to your proposed inspection scope for both axial cracking degradation in the eggerate support region and top-of-tubesheet circumferential cracking degradation.

Confirm your plan to perform condition monitoring and an operational assessment based l

on the mid-cycle inspection findings and that the results from these efforts will be included in a report submitted to the NRC.

The need to provide complete justification to support the requested changes and the agreement of the ANO staff to comply with this request was discussed with members of your staff during a telephone call on September 15,1999. Based on that telephone call, our understanding is that l_

the information can be supplied within a few weeks. A mutually agreed upon due date of I

October 15,1999, was established with Mr. Steve Bennett of your staff.

Sincerely, l

ORIG. SIGNED BY M. Christopher Nolan, Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Pro,iect Management i

Office of Nuclear Reactor Regulation Docket No. 50-368 DISTRIBUTION:

Docket File K. Brockman, RIV cc: See next page PUBLIC S. Black PD4-1 r/f l

OGC ACRS To receive a copy of this document, indicate "C" in the box OFFICE PDIV-1/PM C,

PDIV-1/LA EMCB/SC j PDIV-j/pp'S 4

NAME CNolan M L.BerryN M ESullivanh R.Gramkh j

DATE

/0 / 9 /99 '

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DOCUMENT NAME: G:\\PDIV-1\\ANO2\\RAIMA6224.wpd OFFICIAL RECORD COPY l

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