RBG-31428, Responds to Request for Addl Info Re Rev 3 of First 10-yr Interval Inservice Insp Program Plan

Responds to Request for Addl Info Re Rev 3 of First 10-yr Interval Inservice Insp Program Plan

ML20246J951
Person / Time
Site:	River Bend
Issue date:	08/29/1989
From:	Booker J GULF STATES UTILITIES CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RBG-31428, NUDOCS 8909050317
Download: ML20246J951 (6)

Text

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k GULF STATES UTILITIES COMPANY '

POSTOFFICEBOX29S1 BEAUMONT. TEXAS 77704 AREACODE409 838-6031 August 29, 1989 RBG-31428 File Nos. G9.5, C12.5.2 ,

U. S. Nuclear Regu htory Commission Document Cont:.ol Desk WashinFton, D.C. 20555 Gentlemen: - -

River Bend Station - Unit I

_ Docket No. 50-458 o Gulf States Utilities Company (GSU) is responding to your request for additional information dated July 5, 1989 concerning Revision 3 of the First Ten-Year Interval Inservice Iospection Program Plan for River Bend Station. -

Should you have any questions, please contact Mark S. Feltner of my office at (504) 381-4199.

Sincerely, E. &&

J. E. r,ooker 2.

Manager-River Bend Oversight River Bend NucI' Group

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1 Attachments l ec: Walt Paulson, Project Manager ,

Project Directorate-IV Division of Reactor Projects - III, IV, V Special Prcjects 9ffice of Nuclear Reactor Regulation Oshington, D.C. 20555 Senior Resident Inspector P.O. Box 1051 St, Trancisv111e, LA 70775 -

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ATTACHMENT 1 NRC Comment: In Revision 3 of the ISI Program Plan, the number.of surface examination of Class 2 piping welds (Item Numbers C5.11 and.C5.31) in the Emergency Core Cooling Systeme [(Residual ~ Heat Removal (RHR), High Pressure Core Spray (CSH) and Low Pressure Core Spray (CSL)].has been reduced from approximately 462 to 363 velds wich no discussion or explanation. Discuss why the sampling of L Class 2 piping welds has been significantly reduced after approval of the previous revision of the ISI Program Plan.

GSU Reply: The reason for the requested reduction of Class 2 welds in the ECCS systems is that GSU c:onsidered the type of weld in question (Figure 1) to be exempt from ASME Section XI applicability. Table C-F of ASME B&PV Code, Section XI-Division 1, 1974 Edition with Addenda thrcugh Summer 1975' states that branch connections are examinable. However, the aforementioned weld examination reduction in the River Bend Station ISI Program Plan. involved 93 welds (Attachment 2) of branch connections with nominal branch pipe size less than four inches. Paragraph IWC-1220d of the ATME B&PV Code,Section XI Division 1,.1974 Edition with Addenda through L Summer 1975 provides guidance fer the exemption of such welds with nominal branch pipe cire less than four inches.

i i GSU has not removed any ASME B6FV Code Section XI -

Division 1, Item C5.11 welds associated with ECCS systems from the IS1 Program Plan pending NRC approval.

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ATTACHMENT 2 Listed below are'the ninety-three ECCS welds that are considered exempt by the ASME B&PV Code,Section XI - Division 1. Paragraph IWC-1220d:

ICSH*010A-SWO11 1RHS*033A-SW006 1RHS*063A-SW016 ICSH*012B-FWD 11 1RHS*033A-SWO10 1RHS*070B-SWOO2 1CSH*012B-SW005 1RHS*036b-SWOO5 1RHE*070P-SWOO6 1CSH*017A-SWOO9 1RHS*084A-FW016 1RHS*074A-SWOO2 1CSH*017A-SWO10 1RHS*084A-SWO11 1RHS*074A-SW005 1CSH*017A-SWO11 1RHS*231Al-FWOO2 1RHS*075A-SWO36 1CSH*034A-SWOO4 1RHS*018A-SWOO4 1RES*075A-SWO37 1CSH*034A-SWOO7 1RHS*021A-SWO36 1RHS*075A-SWO40 ICSH*004A-SW006 1RHS*065A-SWO20 1RHS*080A-SWOO6 1CSH*004A-SWOO7 1RHS*066A-FW001 1RHS*089A-FWOO6 1CSH*004A-SWOO8 1RHS*066A-SW005 1RHS*089A-FWO15 1CSH*014B-SW004 1RHS*069A-SWO23 1RHS*107B-FWO25 1CSH*014B-SWOO5 1RHS*017A-SWOO3 1RHS*107B-SWOO4 1CSH*020A-SW005 1RHS*068A-FWO12 1RHS*107B-SW011 1CSH*020A-SWOO6 1RHS*008A-FWOO7 1RHS*107B-SW012 1CSH*020B-FW012 1RHS*008B-SWO14 1RHS*107C-FWO22 1CSH*020B-FW017 1RUS*008C-SW018 1RHS*107C-SW018 1CSH*020B-FWO18 1RHS*061B-SWO13 1RHS*109A-FWO14 1CSH*020B-SWO14 1RES*061B-SWO14 1RHS*109A-FW015 1CSH*020B-SWD16 1RHS*061C-SW018 1RHS*055A-SWC20 1CSL*042A-SWOO7 1RHS*061C-SWO23 1RHS*055A-SWO22 1CSL*004A-FWO21 1RHS*028B-SWO24 1RHS*032A-SW001 1CSL*004A-SWOO6 1RHS*028B-SWO27 1RHS*039A-FW005 1CSL'*004A-SWOO7 1RHS*0280-SWO30 1RHS*080A-SW001 1CSL*004A-SWO26 1RHS*028C-SWO31 1RHS*003A-FWO22 1CSL*001A-FW012 1RHS*032A-FWOO9 1RHS*006A-FWO10 ICSL*001A-SWOO7 1RHS*039A-FWOO8A ICSL*001B-SWO26 1RHS*039A-FWO10 ICSL*001B-SWO27 1RHS*039A-SWOO4 1CSL*001B-SWO28 1RHS*039A-SWOO5 ICSL*001B-SWO29 1RHS*039B-FWO18 1CSL*001B-SWO30 1RHS*044A-FWO25 1CSL*001B-SWO33 1RHS*044A-SWOO2 1RRS*063A-FWO10

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, . - _ - m ATTAC WENT 3 NRC Comment: ASME Code Cases N-62-2, N&119-4, N-322, and N-334 are not. referenced in Regulatory Guide 1.147 as NRC approved code cases. Therefore, these code cases, as referenced in Section 3.0 of the ISI Plan, should not be used without specific NRC approval. NRC Regulatory Guide 1.147. Patagraph C.4 states, " Code Cases that are not on the approved list of this guide (Paragraph C.1) or other regulatory guides, or for which authorize. tion by the commission has not been granted, are not acceptable on a generic basis." The staff notes that the licensee responded to the NRC January 21, 1987 request for additional information by deleting reference to Code Cases N-322 and N-334 from the " preliminary Revision 2" of the ISI Program Plan. Code cases N-62-2 and N-119-4 were then referenced in the licensee's February 27, 1987 submittal of Revision 2 of the ISI Program Plan and all four code cases are referenced in Revision 3 of the ISI Progtam Plan. Provide references or documentation demonstrating that the commission has granted specific approval for the use of the subject code cases at River Bend Station-Unit 1.

GSU Reply: GSU is not requesting the NRC to approve the use of the aforementioned code cases at RBS. The code cases were only used as technical references while developing the RBS ISI Program Plan Requests for Relief. GSU is currently utilizing the Requests for Relief granted in your letter dated October 20, 1987.

ASME Code Cases N-332 and N-334 were added as technical reference to the ISI Program Plan for internal information and reference only. The overview of these code cases was the basis for initiation and submittal of River Bend Station Request for Relief RR0005.

ASME Code Cases N-62-2 and N-119-4 were added as technical references to the ISI Program Plan for internal infornstion and reference only. The overview of these code cases was the basis for initiation and submittal of River Berd Station Request for Relief RR9009.

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ATTACHMENT 4 NRC Comment: Request for Relief RR0005: This request for relief was previously granted in the October 20, 1987 Safety Evaluation (SE). In the original relief request, a significant percentage (70%) of the Code-required examination coverage was reduced from 70 to 0% for four integrally welded attachments with no discussion or explanation. Provide technical justifications as to why the examination coverage was reduced after relief was granted in the October 20, 1987 SE and revise the relief request accordingly.

CSU Reply: The reason for the coverage reduction on Request for Relief RR0005 was a typographical error made on Revision 2 of the Request for Relief. The drawings provided with Revision 2 clearly revealed that 0% of the internal flued-end penetration welds (SW35B) are examinable.

However, the external flued-end weld penetration welds (SW35C) will continue to have a minimum surface examination coverage of 70%.

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