ML20003D731

Forwards Responses to FSAR Questions 121.30 & 121.31 in Response to NRC Request.Calibr Blocks Are Clad in Accordance W/Asme,Section Xi,Paragraph I-3122.No Exams Are Planned for Containment Spray Sys

ML20003D731
Person / Time
Site:	Summer
Issue date:	03/26/1981
From:	Nichols T SOUTH CAROLINA ELECTRIC & GAS CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8103310366
Download: ML20003D731 (4)

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SOUTH CAROLINA ELECTRIC a GAS COMPANY POST orFICE SOE 764 COtuMelA. SOUTM CAROLINA 29218 T. C. NICHOLs, JR.

vicie.<, .. o.w ouci,m, March 26, 1981-Noctrae Oeraarioses Mr. Ilarold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Virgil C. Summer Nuclear Station Docket No. 50/395 FSAR Questions on Preservice Inspection Plan

Dear Mr. Denton:

South Carolina Electric and Gas Company, acting for itself and as agent for South Carolina Public Service Authority, hereby forwards forty-five copies of our responses to FSAR questions 121.30 and 121.31 as requested. These questions and responses will be included in the next FSAR revision.

If there are any questions, please contact me at your convenience.

Very truly yours, L. /

T.C. Nichols, Jr.

ARK /TCN/bsg I

ATTACIIMENT cc: V.C. Summer G.H. Fischer T.C. Nichols, Jr.

C.A. Price D.A. Nauman i

W.A. Williams, Jr. -

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A.A. Smith ,

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B.A. Bursey

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121.30 To complete our evaluation of the applicant's Preservice Inspection Plan, Revision 1, we will require the specific information requested in Question 121.24, as follows:

A. Vessel Calibration Blocks Page B-29 -- Confirm that the subject calibration blocks used to examine a clad component are clad in accordance with 1-3122 of Section XI.

I B. Class 1 Piping (Category B-J), Page B-32 and Class 2 Piping (Categories C-F and C-G), Page B-41.

Provide a list of the piping welds that cannot be completely examined to Section XI requirements. Estimate the extent of the Section XI requirement that was perfcrmed. State the primary reason that a specific examination is impractical, e.g., support or component restricts acceas, fitting prevents adequate ultrasonic coupling on one side, component to component weld prevents ultrasonic examination, etc.

C. Residual Heat Exchanger, Page B-36. Confirm that the nozzle-to-vessel welds were radiographed during fabrication.

D. Seal Water Heat Exchanger, Page B-37, Reactor Coolant Filter, Page B-38, Seal Water Return Filter, Page B-39, Letdown Re-Heat Heat Exchanger, Page B-40. Describe the examination method and extent of examination coverage during fabrication on these component welds.

121.30 Response:

A. All Calibration Blocks for vessels 2!"$ thick and greater are clad in accordance with Appendix I paragraph I-3122 of Section XI.

B. Where possible, all welds are examined from both sides. In all cases, essentially 100% of the weld is examined in accordance with Section XI. Where essentially 100% of the weld cannot be examined as required by ASME Code,Section XI, IWB-2100, relief requests shall be submitted which include the extent of exami-nation performed and the primary reason complete examination is impractical. Included in these relief requests will be the alternate examination method and/or supplemental examinations (if any), that are performed. A list of these welds, including identification of the individual welds by isometric, weld number, and physical configuration, will be provided where they are known

! to exist following the preservice examination. The preservice l weld inspection will be sufficiently completed in order to

! compile and sub:ait this list by April 30, 1981 as a revision to l the Preservice Plan.

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121.30 Response: (Cont'd.)

C. The nozzle to vessel welds were radiographed during febrica-tion. Records of NDE are microfil=ed and filed on site and subj ect to review.

D. These components were examined at fabrication by penetrant and radiographic examination. Records of NDE are microfilmed and filed on site and subject to review.

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121.31 Paragraph 5's.55a(b)(2)(IV) requires that the containment lient Removal System shall be examined. The PSI Plan states in Section 1.2.4.a.5 (Page B-4) that the containment spray system is exempt from volumetric and surface examination based on IWC-1220(b) of Section XI because the system does not function during normal reactor operation.

Describe the measures or component modifications that would be required to perform a volumetric and/or surface examination of a representative sample of welds during the inservice in-spection program.

121.31 Response:

No examinations are planned for examination of containment spray systems (volume and surface) using IWC-1220(b) of Section XI 1974 Edition with Addenda through Summer 1975, because the system does not function during normal reactor operation.

This system will be considered for future inservice examina-tions consisting of a representative sample of the velds involved, pending the requirements of ASME Code Section XI app 11 cable at the time of inservice examination.

An augmented inspection program for the examination of sensi-tized pipe is also in planning stage for inservice inspection.

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