ML20210A694

Summary of 990628 Meeting with Util in Rockville,Md Re Arkansas Nuclear One,Unit 2 Steam Generator Operational Assessment.List of Meeting Attendees & Licensee Handout Used During Meeting Encl

ML20210A694
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/16/1999
From:	Nolan M NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9907220185
Download: ML20210A694 (49)

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4 UNITED STATES j

l NUCLEAR REGULATORY COMMISSION g WASHINGTON, D.C. 2056H001 July 16, 1999

• • • • • /

FACILITY: Entergy Operations, Inc.

LICENSEE: Arkansas Nuclear One, Unit 2

SUMMARY

OF JUNE 28,1999, MEETING WITH ENTERGY OPERATIONS  !

INC., REGARDING THE ARKANSAS NUCLEAR ONE, UNIT 2 (ANO-2), STEAM  !

GENERATOR OPERATIONAL ASSESSMENT On June 28,1999, representatives of the U. S. Nuclear Regulatory Commission (NRC) and i Entergy Operations, Inc. (the licensee), met to discuss the ANO-2 steam generator (S/G) operational assessment. This meeting was held at NRC Headquarters in Rockville, Maryland.

A notice of this meeting was issued on June 9,1999. Enclosure 1 is a list of attendees. i Enclosure 2 is the licensee's handout used during the meeting. )

The ANO-2 S/G operational assessment documented an evaluation performed by the licensee to justify continued operations until a planned fall 1999 mid-cycle outage. This mid-cycle outage would be taken to support S/G tube inspections. The licensee performed a probabilistic  !

evaluation which concluded that the probability of burst at 3 times the normal operating differential pressure between the primary and secondary side of the S/G at the end of the planned operating interval was 9.2 x 10E-2. In addition, the S/G operational assessment discussed the allowances for an increase in hot leg temperature and the corrective actions taken to address an S/G tube in-situ pressure test failure (i.e., an axially flawed S/G tube burst at less than 3AP during an in-situ pressure test) during the last inspection. ANO-2 is currently in its last operating r/cle with its original S/Gs. The licensee reaffirmed its intentions to replace the S/Gs during the fall 2000 refueling outage.

The NRC staff stated that they appreciated the information and additional details; however, the staff would be requesting the licensee to submit additional information regarding various parameters and inputs used in the probabilistic evaluation. This information would be requested in order for the staff to independently verify the adequacy and accuracy of the licensee's predictive model.

l The licensee stated that all of the significant circumferential cracks detected at the hot leg top-of-tubesheet (TTS) during previous inspections appear to have been located in specific regions of the S/G. The most recent operational assessment did not indicate a need to examine the S/Gs for these circumferential cracks during the fall 1999 mid-cycle outage. The licensee indicated that it would be prudent to examine these localized areas during the mid-cycle outage. However, the current technical specifications have an inspection expansion criteria that would most likely require a 100 percent examination. The licensee stated that it I[ ,

,940 f 9907220185 990716 PDR ADOCK 05000368 P PDR

plans to submit an amendment request to limit the inspection expansion criteria for the mid-cycle inspection of TTS circumferential cracks. The licensee also stated that this enange would result in substantial reductions in cost, exposure, outage length, and time at reduced inventory.

Original signed by 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

Enclosures:

As stated (2) cc w/encis: See next page I

I l

DISTRIBUTION:

HARD COPY E-MAIL Docket JZwolinski/SBlack EMurphy )

PUBLIC SRichards KWichman 1 PDIV-1 RF DLange CBeardslee OGC KBrockman, RIV SCoffin j ACRS NHilton i To receive a copy of this document, indicate "C" in the b >x t OFFICE PDIV-1/PM C PDIV 1/M N PDIV-1/';C G Je NAME CNolan:db M LBerry [ RGramm b DATE 1/ /6 /99 C /j( /gh g/ gg /99 ,

DOCUMENT NAME: G:\PDIV-1\ANO2\mts6-28.wpd OFFICIAL RECORD COPY

Arkansas Nuclear One cc:

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 Jackson, MS 39286-1995 -

Wise, Carter, Child & Caraway

- Director, Division of Radiation P. O. Box 651 Control and Emergency Management - Jackson, MS 39205 Arkansas Department of Health -

4815 West Markham Street, Slot 30 Mr. C. Randy Hutchinson Little Rock, AR 72205-3867- Vice President Operations, ANO Entergy Operations, Inc.

Winston & Strawn >

1448 S. R. 333 1400 L Street, N.W. Russellville, AR 72801 Washington, DC 20000-3502 Manager, Rockville Nuclear Licensing Framatone Technologies '

1700 Rockville Pike, Suite 525 '

~ Rockville, MD 20852 Senior Resident inspector >

' U.S. Nuclear Regulatory Commission -

P. O. Box 310 London, AR 72847 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 61i Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope County Courthouse ,

- Russellville, AR 72801 l l

4 l

l May 1999 i

-4 l

k:

ATTENDANCE LIST PUBLIC MEETING HELD JULY 28,1999 Name Oraanization Telephone No.

Chris Nolan NRC/NRR 301-415-1320 Nick Hilton NRC/NRR 301-415-1314 Steve Brown APTECH Engineering 740-452-2431 Bill Hannaman DS&S/SAIC 858-826-4964 Mike Lloyd Entergy Operations Inc. 501-858-4654 Mark Smith Entergy Operations Inc. 501-858-4901 Brian Woodman APTECH Engineering 415-745-7000 Russell Cipolla APTECH Engineering 415-745-7000 Mark Whitt Entergy Operations, Inc. 501-858-4907 Darol Harrison Entergy Operations, Inc. 501-858-4909 4 Rick Lane Entergy Operations, Inc. 501-858-4400 Bob Bement Entergy Operations, Inc. 501-858-3282 Craig Anderson Entergy Operations, Inc. 501-858-3110 Dale James Entergy Operations, Inc. 501-858-4619 Emmett Murphy NRC/NRR 301-415-2710 Keith Wichman NRC/NRR 301-415-2757 Cheryl Beardstee NRC/NRR 301-415-2751 Pat Heasier Pacific Northwest National Laboratory 509-375-2099 Stuart Richards NRC/NRR 301-415-1395 Stephanie Coffin NRC/NRR 301-415-2778 Leslie Collins ABB/CEND 301-881-7012 David Stellfox McGraw Hill 202-383-2162 Enclosure 1 l

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