ML20149E911

Submits Response to NRC 940526 RAI on Relief Request 93-02, Clarifying That Relief Request for Relief in Accordance W/ 10CFR50.55a from ASME Section XI Code Requirement,Including Listing of Components Shown in Plant ISI Plan

ML20149E911
Person / Time
Site:	Catawba
Issue date:	07/20/1994
From:	Rehn D DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TAC-M88068, TAC-M88069, NUDOCS 9408080176
Download: ML20149E911 (6)

Text

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\\ ice (+esident 1800 ConcordRoad (803)&113205 Offne York. SC29NS (803)&113CGlax DUKEPOWER July 20,1994 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Reply to Request for Additional Information on Relief Request No. 93-02 TAC Nos. M88068 and M88069

Reference:

Ixtter from NRC to David L. Rehn, dated May 26,1994 Gentlemen:

Please And our reply to your Request for Additional Information (RAI), as transmitted in the reference letter. This RAI requested responses to the following questions:

1.

The relief request, in item I, refers to a request for an exemption. Please clarify whether the request is for an exemption pursuant to 10 CFR 50.12 or for relief pursuant to 10 CFR 50.55a.

2.

Identify the specific welds that are the subject of the request.

3.

Discuss the schedule for inspection of those welds set forth by the Code, the results to date, and the proposed alternate schedule.

4.

Discuss the interval between inspections for the subject welds that will result from the proposed alternate inspection schedule.

Please refer to the attachment for our reply to the above questions. If you have any questions, please call L.J. Rudy at (803) 831-3084.

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9400080176 940720 PDR ADDCK 05000413 Lj(,

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,Docu nent Control Desk Page 2 July 20,1994 Very truly your,

D.L. Rehn U R/s xc (with attaciunent):

S.D. Ebneter, Regional Administrator Region II R.J. Freudenberger, Senior Resident Inspector R.E. Martin, Senior Project Manager l

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IiEQUFST FOR ADDITIONAL INFORMATION ON RELIEF REQUEST NUMBER 93-02, CATAWBA NUCLEAR STATION, UNITS 1 & 2 1.

The intent of this Relief Request is to ask for relief in accordance with 10 CFR 50.55a from an ASME Section XI Code requirement that has been detennined to be impractical.

2.

The components for which this relief is requested are the Reactor Vessel Outlet Nmzle-to-Vessel Welds and Inside Radius Sections. The followin; is a specific list of these components as shown in the Catawba Units 1 & 2 Inservice Inspection Plan:

CATAWBA UNIT 1 REACTOR VESSEL NOZZLE-TO-VESSEL WELDS SECTION XI WELD ID DESCRIPTION ITEM NO.

B03.090.005 1RPV-W15 OUTLET NOZZLE A TO SHELL 22 DEGREES UT FROM VESSEL ID B03.090.005A 1RPV-W15 OUTLET NOZZLE A TO SHELL 22 DEGREES UT FROM NOZZLE ID B03.090.006 1RPV-W16 OUTLET NOZZLE D TO SHELL 158 DEGREES UT FROM VESSEL ID B03.090.006A 1RPV-W16 OUTLET NOZZLE D TO SHELL 158 DEGREES UT FROM NOZZLE ID B03.090.007 1RPV-W17 OUTLET NOZZLE E TO SHELL 202 DEGREES UT FROM VESSEL ID B03.090.007A 1RPV-W17 OUTLET NOZZLE E TO SHELL 202 DEGREES UT FROM NOZZLE ID B03.090.008 1RPV-W18 OUTLET NOZZLE H TO SHELL 338 DEGREES UT FROM VESSEL ID B03.090.008A 1RPV W18 OUTLET NOZZLE H TO SHELL 338 DEGREES UT FROM NOZZLE ID

REACTOR VESSEL NOZZLE INSIDE RADIUS SECTIONS L

SECTION XI WELD ID DESCRIPTION ITEM NO.

E03.100.005 1RPV-W15 OUTLET NOZZLE A TO SHELL 22 DEGREES UT FROM NOZZLE ID I_

B03.100.006 1RPV-W16 OUTLET NOZZLE D TO SHELL 158 DEGREES UT FROM NOZZLE ID B03.100.007 1RPV-W17 OUTLET NOZZLE E TO SHELL 202 DEGREES UT FROM NOZZLE ID

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B03.100.008 1RPV-W18 OUTLET NOZZLE H TO SHELL 338 DEGREES UT FROM NOZZLE ID CATAWBA UNIT 2 REACTOR VESSEL NOZZLE-TO-VESSEL WELDS SECTION XI WELD ID DESCRIPTION ITEM NO.

B03.090.005 2RPV-107-121 A OUTLET NOZZLE A TO SHELL 22 DEGREES UT FROM VESSEL ID B03.090.005A 2RPV-107-121A OUTLET NOZZLE A TO SHELL 22 DEGIEES UT FROM NOZZLE ID B03.090.006 2RPV-107-121B OUTLET NOZZLE B TO SHELL 158 DEGREES UT FROM VESSEL ID B03.090.006A 2RPV-107-121B OUTLET NOZZLE B TO SHELL IS8 DEGREES UT FROM NOZZLE ID B03.090.007 2RPV-107-121C OUTLET NOZZLE C TO SHELL 202 DEGREES UT FROM VESSEL ID l

B03.090.007A 2RPV-107-121C OUTLET NOZZLE C TO SHELL 202 DEGREES UT FROM NOZZLE ID B03.090.008 2RPV-107-121D OUTLET NOZZLE D TO SHELL 338 DEGREES UT FROM VESSEL ID B03.090.008A 2RPV-107-121D OUTLET NOZZLE D TO SHELL 338 DEGREES UT FROM NOZZLE ID REACTOR VESSEL NOZZLE INSIDE RADIUS SECTIONS SECTION XI WELD ID DESCRIPTION ITEM NO.

B03.100.005 2RPV-107-121 A OUTLET NOZZLE A TO SHELL 22 DEGREES UT FROM NOZZLE ID B03.100.006 2RPV-107-121B OUTLET NOZZLE B TO SHELL158 DEGREES UT FROM NOZZLE ID B03.100.007 2RPV-107-121C OUTLET NOZZLE C TO SHELL 202 DEGREES UT FROM NOZZLE ID B03.100.008 2RPV-107-121D OUTLET NOZZLE D TO SHELL 338 DEGREES UT FROM NOZZLE ID 3.

CODE REQUIREMENT: ASME Section XI, Table IWB-2500-1; Category B-D, Item Numbers B3.90 and B3.100, NOTE (3) : At least 25% but not more than 50% (credited) of the nozzles shall be examined by the end of the first period and the remainder by the end of the third inspection period of each inspection interval.

RESULTS TO DATE: The nozzle examinations referenced above were performed during the first inspection period for Catawba Units 1&2 to meet this First Ten Year Interval requirement. No reportable indications were detected. These nozzles were again examined during the third inspection period of the First Ten Year Interval for Catawba Unit 1 in conjunction with the Reactor Vessel Examination. No reportable indications were detected. For Catawba Unit 2, these nozzle examinations will be performed during the third

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inspection period of the First Ten Year Interval in conjunction with the Reactor Vessel Examination.

PROPOSED ALTERNATE SCHEDULE: Under the proposed alternate inspection schedule, these nozzle examinations will not be scheduled for Catawba Units 1&2 Second Ten Year Interval during the first inspection period but will be scheduled and examined during the third inspection period in conjunction with the second interval Reactor Vessel Examination.

4.

We will continue to schedule these Reactor Vessel Outlet Nozzle To Vessel Welds and Inside Radius Sections in conjunction with the Reactor Vessel Examination which will be in the third inspection period of each ten year interval. The interval between examinations using this proposed alternate schedule l

would be approximately ten years.

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