ML20133B473

Forwards RAI in Response to Ltr Re Insvc Insp of Once Through Steam Generator Tubes at Arkansas Nuclear One

ML20133B473
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/31/1996
From:	Salehi K NRC (Affiliation Not Assigned)
To:	Hutchinson C ENTERGY OPERATIONS, INC.
References
TAC-M97485, NUDOCS 9701030205
Download: ML20133B473 (4)

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December 31, 1996 l Mr. C. Randy Hutchinson i Vice President, Operations ANO I .Entergy Operations, Inc.

1448 S. R. 333 Russellville, AR 72801

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO INSERVICE INSPECTION i 0F THE ONCE THROUGH STEAM GENERATOR (OSTG) TUBES AT ARKANSAS l NUCLEAR ONE, UNIT 1 (ANO-1) (TAC NO. M97485)  ;

Dear Mr. Hutchinson:

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By letter dated November 21, 1996, Entergy Operations, Inc. submitted a report i on the results of the inservice inspection of the once through steam generator  :

(OSTG) tubes at Arkansas Nuclear One, Unit 1 (ANO-1). The Technical '

l Specification 4.1.18.6 requires the complete results of each inservice inspection ~ of the OSTG tubes to be submitted to the Nuclear Regulatory Commission within 45 days of the. completion of the inspection. As a result of a review of your letter. dated November 21, 1996, the staff identified areas where additional information is needed to clarify the results of the i inspection.

Please provide your response to the enclosed questions within 30 days so that our review of the this matter can proceed on schedule. If you need l clarification of the staff's request, please contact me at (301) 415-1367.

Sincerely, ,

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ORIGINAL SIGNED BY:

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K. Salehi, Acting Project Manager Project Directorate IV-1  ;

Division of Reactor Projects III/IV Office of4 Nuclear Reactor Regulation

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Docket No. 50-313 +> .

Enclosure:

Request for Additional Informat on , , ,

4 cc w/ enc 1: See next page ,

DISTRIBUTION: 1, , ,

CDocket FileJ PUBLIC PD4-1 r/f' '

K. Salehi C. Hawes OGC i ACRS J. Dyer, RIV J. Roe i E. Adensam (EGA1)

Document Name: AR97485.RAI 1 0FC NAME (A)PM/PD4-1 KSalehhw (A)LA/PD4-2 CHawes (4TJN NE M NE #I l l

DATE /2/3//96 n / S/96 if COPY YES/NO YES/N0 0FFICIAL RECORD COPY Q >

J 0300In 9701030205 961231 l

1 PDR ADOCK 05000313 l w 0 __

PDR _J

pme uq% u,mo .rm.

g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. SpeeHooi

• • • • • December 31, 1996 Mr. C. Randy Hutchinson Vice President, Operations AND Entergy Operations, Inc.

1448 S. R. 333 Russellville, AR 72801

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO INSERVICE INSPECTION 0F THE ONCE THROUGH STEAM GENERATOR (OSTG) TUBES AT ARKANSAS NUCLEAR ONE, UNIT 1 (ANO-1) (TAC NO. M97485)

Dear Mr. Hutchinson:

By letter dated November 21, 1996, Entergy Operations, Inc. submitted a report on the results of the inservice inspection of the once through steam generator (OSTG) tubes at Arkansas Nuclear One, Unit 1 (ANO-1). The Technical Specification 4.1.18.6 requires the complete results of each inservice inspection of the OSTG tubes to be submitted to the Nuclear Regulatory Commission within 45 days of the completion of the inspection. As a result of a review of your letter dated November 21, 1996, the staff identified areas where additional information is needed to clarify the results of the inspection.

Please provide your response to the enclosed questions within 30 days so that our review of the this matter can proceed on schedule. If you need clarification of the staff's request, please contact me at (301) 415-1367.

Sincerely, J

K. Salehi, Acting Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-313

Enclosure:

Request for Additional Information -

cc w/ enc 1: See next page l

Mr. C. Randy Hutchinson Entergy Operations, Inc. Arkansas Nuclear One, Unit I cc:

Executive Vice President Vice President, Operations Support

& Chiel Operating Officer Entergy Operations, Inc.

Entergy Operations, Inc. P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 Jackson, MS 39286-199 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 Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.

Washington, DC 20005-3502 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 611 Ryan Plaza Drive, Suite 400 l Arlington, TX 76011-8064 County Judge of Pope County 1 Pope County Courthouse ,

Russellville, AR 72801 l

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j REQUEST FOR ADDITIONAL INFORMATION J

l RELATED TO INSERVICE INSPECTION REPORI 0F THE ONCE THROUGH STEAM GENERATORS

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ENTERGY OPERATIONS INC.

e l ARKANSAS NUCLEAR ONE. UNIT 1 (ANO-1) l DOCKET NO. 50-313

1. Please discuss the types of coils used in the motorized rotating pancake 4 coil probe (MRPC)(e.g., mid-range 0.115-inch pancake coll).  !

j 2. For the tubes in the "A" and "B" OTSG with free-span axial indications at l dented locations, please state whether these indications were found i during routine examinations using bobbin coil probe and/or the MRPC j probe. Please discuss the nature and the size estimates made for these

degraded indications (i.e., address the structural and leakage integrity of these indications). For the dents with degraded indications, discuss the " size" of the dents with indications in comparison with the size of other dents in the steam generators. Discuss the expansion criteria used i and the technical basis for the criteria. ,

1 i 3. Discuss the nature of the indications detected in the sleeved portion of  :

i the tubes (including both parent tube and the sleeve) and at the upper i

! roll transition (e.g., an axially oriented defect indicative of primary l l water stress corrosion cracking). Discuss the structural and leakage

.i integrity of these indications.

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4. Discuss the nature of the axial indications at the lower tubesheet as

! determined from non-destructive examination. For example, address i whether the indications were in the sludge pile region, above the top of the tubesheet, in the tubesheet crevice region, etc. Discuss the i structural and leakage integrity of these indications. I

5. The inspection report stated that the sleeve indications were considered i as artifacts from the sleeve installation and/or also due to the enhanced i eddy current testing method. It also stated that the sleeve inspection

] techniques prior to 1995 were not considered to be adequate for detection of these type of indications. Provide the basis for the two statements.

. Provide any laboratory testing ahd/or available laboratory test data

which would support the above statements.

1 6. The staff recognizes that several tube sections were removed for destructive examination during this outage and that the results will be provided to the NRC when available. However, the above questions apply to the results from the non-destructive examination of the tubes.

Discuss the schedule for the examination of the pulled tube sections. As 4

discussed during a telephone conversation during the outage, discuss whether detailed non-destructive examination results for the pulled tubes will be provided prior to commencing destructive examination.

ENCLOSURE 3

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