ML20205D536

Forwards Ser,Accepting Util 980107 Request for Alternative to Augmented Reactor Pressure Vessel Exam Requirements for Plant,Unit 1 Pursuant to 10CFR50.55a(g)(6)(ii)(A) for First 10-year Insp Interval.Technical Ltr Rept Also Encl

ML20205D536
Person / Time
Site:	River Bend
Issue date:	03/26/1999
From:	Dick G NRC (Affiliation Not Assigned)
To:	Edington R ENTERGY OPERATIONS, INC.
Shared Package
ML20205D542	List: ML20205D536 ML20205D548
References
TAC-MA0621, TAC-MA621, NUDOCS 9904020233
Download: ML20205D536 (3)

Text

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March 26, 1999

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Mr. Randall K. Edington a Vice President - Operations -

Entergy Operations,5c.

River Bend Station -

P. O. Box 220 St. Francisville, LA 70775

SUBJECT:

EVALUATION OF THE ALTERNATIVE TO AUGMENTED REACTOR PRESSURE VESSEL EXAMINATION REQUIREMENTS FOR RIVER BEND STATION, UNIT 1 (TAC NO. MA0621)

Dear Mr. Edington:

By letter dated January 7,1998, you submitted a request to the Nuclear Regulatory Commission (NRC) staff for an alternative to the augmented reactor pressure vessel examination requirements for River Bend Station, Unit 1, pursuant to Title 10 of the Code of Federal Reaulations (10 CFR), Section 50.55a(g)(6)(ii)(A).

The NRC staff, with technical assistance from its contractor, the Idaho National Engineering and Environmental Laboratory (INEEL), has reviewed and evaluated the information provided in i support of an attemative to the augmented reactor pressure vessel examination. The staff adopts the evaluation and conclusions presented in the Technical Letter Report (TLR) prepared

.by INEEL. The enclosed safety evaluation incorporated the TLR and its findings. Based on the

Information submitted, the staff concludes that you have maximized examination coverage to the extent practical, and that imposing additional examinations would result in a considerable -

hardship without a compensating increase in the level of quality and safety. Therefore, your proposed alternative, the augmented reactor pressure. vessel examination of the accessible weld volume in combination with future reactor pressure vessel examinations, provides an acceptable level of quality and safety and is authorized pursuant to ,10 CFR 50.55a(a)(3)(ii) and 10 CFR 50.55a(g)(6)(ii)(A)(5) for the first 10-year inspection interval.

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Sincerely,

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,GeorgsDick, Acting Director '

(i Project Directorate IV-1 p Division of Licensing Project Management  ;

Office of Nuclear Reactor Regulation f' i

Docket No. 50-458 d

Enclosure:

Safety Evaluation

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%*****/ March 26, 1999 l Mr. Randall K. Edington Vice President - Operations Entergy Operations, Inc. 4 River Bend Station P. O. Box 220 St. Francisville, LA 70775

SUBJECT:

EVALUATION OF THE ALTERNATIVE TO AUGMENTED REACTOR PRESSURE VESSEL EXAMINATION REQUIREMENTS FOR RIVER BEND STATION, UNIT 1 (TAC NO. MA0621) 1

Dear Mr. Edington:

By letter dated January 7,1998, you submitted a request to the Nuclear Regulatory Commission (NRC) staff for an alternative to the augmented reactor pressure vessel examination requirements for River Bend Station, Unit 1, pursuant to Title 10 of the Code of Federal Reautations (10 CFR), Section 50.55a(g)(6)(ii)(A).

The NRC staff, with technical assistance from its contractor, the Idaho National Engineering and Environmental Laboratory (INEEL), has reviewed and evaluated the information provided in support of an altemative to the augmented reactor pressure vessel examination. The staff adopts the evaluation and conclusions presented in the Technical Letter Report (TLR) prepared l by INEEL. The enclosed safety evaluation incorporated the TLR and its findings. Based on the information submitted, the staff concludes that you have maximized examination coverage to the extent practical, and that imposing additional examinations would result in a considerable hardship without a compensating increase in the level of quality and safety. Therefore, your proposed alternative, the augmented reactor pressure vessel examination of the accessible weld volume in combination with future reactor pressure vessel examinations, provides an acceptable level of quality and safety and is authorized pursuant to 10 CFR 50.55a(a)(3)(ii) and 10 CFR 50.55a(g)(6)(li)(A)(5) for the first 10-year inspection interval.

Sincerely,

{h TAfi George Dick, Acting Director Project Directorate IV-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-458

Enclosure:

Safety Evaluation

cc w/ encl

See next page 1

'9

< Mr. Randall K. Edington Entergy Operations, Inc. River Bend Station cc:

Winston & Strawn Executive Vice President and 1400 L Street, N.W. Chief Operating Officer Washington, DC 20005-3502 Entergy Operations, Inc.

P. O. Box 31995 Manager- Licensing Jackson, MS 39286 Entergy Operations, Inc.

River Bend Station General Manager - Plant Operations  !

P. O. Box 220 Entergy Operations, Inc. l St. Francisville, LA 70775 River Bend Station  !

P. O. Box 220 l Senior Resident inspector St. Francisville, LA 70775 i P. O. Box 1050 St. Francisville, LA 70775 Director - Nuclear Safety Entergy Operations, Inc.

President of West Feliciana River Bend Station Police Jury P. O. Box 220 P. O. Box 1921 St. Francisville, LA 70775 St. Francisville, LA 70775 Vice President - Operations Support l Regional Administrator, Region IV Entergy Operations, Inc.

U.S. Nuclear Regulatory Commission P. O. Box 31995 611 Ryan Plaza Drive, Suite 1000 Jackson, MS 39286-1995 Arlington,TX 76011 Attorney General Ms. H. Anne Plettinger State of Louisiana 3456 Villa Rose Drive P. O. Box 94095 Baton Rouge, LA 70806 Baton Rouge, LA 70804-9095 l Administrator Wise, Carter, Child & Caraway Louisiana Radiation Protection Division P. O. Box 651 P. O. Box 82135 Jackson, MS 39205

. Baton Rouge, LA 70884-2135 ,

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