ML20248F445

From kanterella
Jump to navigation Jump to search

Forwards RAI to Complete Review of Util Request Re Second Inservice Insp Program Plan Request for Relief.Requests Response by 980710
ML20248F445
Person / Time
Site: River Bend Entergy icon.png
Issue date: 06/02/1998
From: Wigginton D
NRC (Affiliation Not Assigned)
To: Mcgaha J
ENTERGY OPERATIONS, INC.
References
TAC-MA0620, TAC-MA620, NUDOCS 9806040267
Download: ML20248F445 (5)


Text

!.

  • L

'i Mr. John R. McGaha, Jr. Juns 2, 1998 j Vice President - Operations i Entergy Operations, Inc.

River Bond Station P. O. Box 220 St. Francisville, LA 70775

SUBJECT:

RIVER BEND STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION I

REGARDING SECOND INSERVICE INSPECTION PROGRAM PLAN REQUEST FOR RELIEF (TAC . MA0620)

Dear Mr. McGaha:

1The staff with assistance from its contractor, the Idaho National Engineering and Environmental Laboratory (INEEL), is reviewing and evaluating the River Bend Station, Unit 1, second ten-year

. inservice inspection program plan requests for relief. Entergy Operations, Inc. submitted the request by letter dated January 7,1998. Additional information is required from Entergy Operations, Inc., in order for the staff to complete its review.

It is requested that Entergy Operations, Inc., provide a response by July 10,1998, so that we can meet our original date for completing the review. In order to e'xpedite the review pror:ess, please send a copy of the response to our contractor, INEEL' at the following address:

MichaelT. Anderson s INEEL Research Center.

2151 North Boulevard P.O. Box 1625 Idaho Falls, Idaho 83415-2209 If you have any questions on our request, please call me at 301-415-1301.

Sincerely,-

ORIGINAL SIGNED BY: ,

David L. Wigginton, Sr. Project Manager .

Project Directorate IV-1 Division of Reactor Projects ill/IV i 1

Office of Nuclear Reactor Regulation Docket No. 50-458

Enclosure:

Request for AdditionalInformation cc w/ encl: See next page DISTRIBUTION:

Docket Fih - PUBLIC PD4-1 r/f CHawes DWgginton TGwynn, RIV

< ACRS JHannon OGC EAdensam (EGA1) Q_ l j

! Document Name: RBA0620.RAI /

OFC PM/PC kj y 1.A/PD4-1 PD[ IV-1 NAME DWighvw CHN #

JHannon DATE b/ d-/98 h/h /98 / /98 I

COPY M/NO YES/NO YES/NO .

.-.m OFFICIAL RECORD COPY ;j j 9806040267 980602 m-l- PDR ADOCK 05000458 e PDR

taro p *, UNITED STATES E

NUCLEAR REGULATORY COMMISSION I WASHINGTON, D.C. 3D806-0001

% ,,g */ June 2, 1998 Mr. John R. McGaha, Jr.

Vice President - Operations  ;

Enterg3 Drations,Inc. J River B- ed Station P. O. Box 220 St. Francisville, LA 70775

SUBJECT:

RIVER BEND STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING SECOND INSERVICE INSPECTION PROGRAM PL.AN REQUEST '

FOR RELIEF (TAC NO. MA0620)

Dear Mr. McGaha:

The staff with assistance from its contractor, the Idaho National Engineering and Environmental Laboratory (INEEL), is reviewing and evaluating the River Bend Station, Unit 1, second ten-year inseivice inspection program plan requests for relief. Entergy Operations, Inc. submitted the request by letter dated January 7,1998. Additional information is required from Entergy Operations, Inc., in order for the staff to complete its review, it is requested that Entergy Operations, Inc., provide a response by July 10,1998, so that we can meet our original date for ccmpleting the review. In order to expedite the review process, please send a copy of the response to our contractor, INEEL, at the following address:

MichaelT. Anderson INEEL Research Center 2151 North Boulevard P.O. Box 1625 Idaho Falls, Idaho 83415 2209 If you hava any questions on our request, please call me at 301-415-1301.

Sincerely, David L Wigginton, Sr. Project Manags/

Project Directorate IV-1 Division of Reactor Projects til/IV Office of Nuclear Reactor Regulation Docket No. 50 458 '

Enclosure:

Request for AdditionalInformation cc w/ encl: See next page l

1  !

r i

I .

Mr. John R. McGaha Entergy Operations, Inc. River Bond Station cc:

Winston & Strewn Executive Vice President and 1400 L Street, N.W. Chief Operating Officer t i

Washington, DC 20005-3502 Entergy Operations, Inc. I P. O. Box 31995 Manager- Licensing Jackson, MS 39286 Entergy Operations, Inc. I River Bend Station General Manager- Plant Operations l P. O. Box 220 Entergy Operations, Inc.

St. Francisville, LA 70775 River Bend Station l P. O. Box 220 l

Senior Resident inspector St. Francisville, LA 70775 P. O. Box 1050 L 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 l

St. Francisville, LA 70775 Vice President- Operations Support -

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 Artington, TX 76011 .

Attomey 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 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 l

l I

I l

l

ENTERGY OPERATIONS,INC RIVER BEND STATION, UNIT 1 DOCKET NUMBER 50 458 CML ENGINEERING AND GEOSCIENCES BRANCH DIVISION OF ENGINEERING Reouest for Additional Information (RAl) on the second 10-Year Interval inservice Reauests for BRhtf.

A. Scone / Status of Revjag Throughout the service life of a water-cooled nuclear power facility,10 CFR 50.55a(g)(4) requires that components (including supports) that are classified as American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Class 1, Class 2, and Class 3 meet the requirements, except design and access provisions and preservice examination requirements, set forth in the ASME Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. This section of the regulations also requires that inservice examinations of components and system pressure tests conducted during successive 120-month inspection intervals comply with the requirements in the latest edition and addenda of the Code incorporated i by reference in 10 CFR 50.55a(b) on the date 12 months prior to the start of the interval, f subject to the limitations and modifications listed therein. The components (including supports) may meet examination requirements set forth in subsequent editions and addenda of the Code that are incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Nuclear Regulatory Commission (NRC) approval. The licensee, Entergy Operations, Inc, prepared the second ISI interval program plan to meet the requirements of the 1992 Edition of the ASME Code Section XI. The second 10-year interval began December 1,1997.

As required by 10 CFR 50.55a(g)(5), if the licensee determines that certain Code examination requirements are impractical and requests relief, the licensee shall submit information to the NRC to support that determination.

The staff has reviewed the available information in thesecond ISI interval Relief Requests RR2-0001 througn RR2-0003, submitted January 7,1998. Based on this l

ENCLOSURE l

a review, the staff has concluded that the information and/or clarification described in the next section is required to complete the review. ,

B. Additional Information Reauired Request for Relief RR2-0003 seeks relief from the surface examination requirements for specific Class 2 pump casing welds that are encased in concrete for the second ISI interval. The licensee is proposing to examine the subject welds only if the pump is disassembled for maintenance. However, during the first ISl interval, a relief request was submitted for the same pump casing welds. In the first interval request, an attemative was proposed to include examinations of the accessible portion of the pump casing welds (examination coverage was as high as 80% in some cases). Explain why accessible portions of the subject pump casing welds are not receiving a surface examination during the second interval. Describe the limitations in detail. In addition, explain how the weld numbering convention used during the first interval corresponds to the welds identified in the second interval relief request. How do the welds identified in RR2-0003 correspond with the weld numbers on the attached Figure 1, " Typical Pump Configuration"? Discuss why the total number of welds for which relief is requested is not the same in the first interval request as in the second interval for each of the subject pumps.

i The schedule for timely completion of this review requires that the licensee provides, by the requested date, the above requested information and/or clarifications regarding the second ISl interval relief requests RR2-0001 through RR2-0003.

1 4

2