ML20134P835

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Forwards Safety Evaluation Re Second 10-yr Interval Inservice Insp Program Plan
ML20134P835
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 11/25/1996
From: Beckner W
NRC (Affiliation Not Assigned)
To: Hutchinson C
ENTERGY OPERATIONS, INC.
Shared Package
ML20134P838 List:
References
TAC-M95708, NUDOCS 9611290320
Download: ML20134P835 (3)


Text

. -. -.

Mr. C. Randy Hutchinson _ November 25, 1996 Vice President, Operations ANO d

Entergy Operations, Inc.

1448 S._R. 333 Russellville, AR 72801

SUBJECT:

INSERVICE INSPECTION PROGRAM - REQUEST FOR ALTERNATE EXAMINATION ARKANSAS NUCLEAR ONE, UNIT 1 (ANO-1) STEAM GENERATOR N0ZZLE (TAC NO.

M95708) a
. Dear Mr. Hutchinsor -

.By letter dated June 12, 1996, Energy Operations, Inc. (E01) proposed an

alternative examination for ANO-1 steam generators. Specifically, E01 i proposed to examine all of the Code _ category B-D nozzles on one of the steam generators rather than both steam generators.

l The NRC staff evaluated the Request for Relief No.96-001 to use a sampling i

philosophy and perform volumetric examination on the Class 1 nozzles and inner radius (IR) sections of only one steam generator in lieu of the Code l requirement of volumetric examination of all Class 1 steam generator nozzles E and nozzle IR sections. The staff concluded that: 1) r,ursuant to

! 10 CFR.50.55a(a)(3)(1), the proposed alternative does r.ot provide an acceptable level of quality and safety; 2) pursuant to 10 CFR

}

1-50.55a(a)(3)(ii), the licensee has not provided a basis for undue hardship, based on the limited number and safety significance of the nozzles; and 3)

pursuant to 10 CFR 50.55a(g)(6)(1), the licensee has.not provided basis for impracticality. Therefore, the licensee's Request for Relief No.96-001 is denied. Enclosure contains the staff's evaluation and conclusions.

Attachment 1 is the Idaho National Engineering Laboratory Technical Letter Reort.

Sincerely, ORIGINAL SIGNED BY:

William D. Beckner, Director Project Directorate IV-1 Division of Reactor Projects III/IV 9611290320 961125 " * "" " * * "

PDR ADOCK 05000313 0 PDR Docket No. 50-313

Enclosure:

Safety Evaluation cc w/ encl: See next page

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CHawes WBeckner J PUBLIC KSalehi - JDyer, RIV fPD4-1r/f JMitchell ACRS JRoe OGC GBagchi EAdensam (EGA1) :TMcLellan Document Name: AR195708.LTR *See previous concurrence 0FC (A)PM/PD4-1 ~ (A)LA/PD4-1 DE/ECG* BC/ECGB* OGC* D/PD4-1 NAME KSalehi:sp N CHawes6rN TMcLellan GBagchi MYoung WBeckN DATE 11/0//96 11Qlc/96 11/05/96 11/05/96 11/19/96 y/gf/96 COPY YES/NO YES/N0 YES/N0 YES/N0 YES/NO YES/N0 2 fl00 <10 0FFICIAL RECORD COPY NRC RLE CEn\TER

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\,,g,,*/ November 25, 1996 Mr. C. Randy Hutchinson Vice President, Operations ANO Entergy Operations, Inc.

1448 S. R. 333 Russellville, AR 72801

SUBJECT:

INSERVICE INSPECTION PROGRAM - REQUEST FOR ALTERNATE EXAMINATION FOR ARKANSAS NUCLEAR ONE, UNIT 1 (ANO-1) STEAM GENERATOR N0ZZLE (TAC NO.

M95708)

Dear Mr. Hutchinson:

J By letter dated June 12, 1996, Energy Operations, Inc. (E01) proposed an alternative examination for ANO-1 steam generators. Specifically, E01 proposed to examine. all of the Code category B-D nozzles on one of the steam generators rather than both steam generators.

The NRC staff evaluated the Request for Relief No.96-001 to use a sampling philosophy and perform volumetric examination on the Class 1 nozzles and inner radius (IR) sections of only one steam generator in lieu of the Code  ;

requirement of volumetric examination of all Class 1 steam generator nozzles I and nozzle IR sections. The staff concluded that: 1) pursuant to 10 CFR 50.55a(a)(3)(i),.the proposed alternative does not provide an acceptable level of quality and safety; 2) pursuant to '10 CFR .

50.55a(a)(3)(ii), the licensee has not provided a basis for undue hardship, based on the limited number and safety significance of the nozzles; and 3) pursuant to 10 CFR 50.55a(g)(6)(1), the licensee has not provided basis for 4 impracticality. Therefore, the licensee's Request for Relief No.96-001 is denied. Enclosure contains the-staff's evaluation and conclusions.

Attachment 1 is the Idaho National Engineering Laboratory Technical Letter Report.

Sincerely, Q Ohh ^

William D. Beckner, Director Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-313

Enclosure:

Safety Evaluation cc.w/ encl: See next page

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

Executive Vice President Vice President, Operations Support j

& Chief Operating Officer Entergy Operations, Inc.  !

Entergy Operations, Inc. P. O. Box 31995 l 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 l 4815 West Markham Street, Slot 30 i Little Rock, AR 72205-3867 l

1 Winston & Strawn 1400 L Street, N.W. I Washington, DC 20005-3502 '

l Manager, Rockville Nuclear Licensing l Framatone Technologies '

1700 Rockville Pike, Suite 525 Rockville, MD 20852 Senior Resident Inspector U.S. Nuclear Regulatory Commission 4 P. O. Box 310 London, AR 72847 '

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