ML17261B092

Responds to 900709 Request for Addl Info Re Containment Integrity Insp.Util Will Provide Preliminary Results by 900716 Re Where Groundwater Entering Annular Access Area. Meeting Proposed for Wk of 900723

ML17261B092
Person / Time
Site:	Ginna
Issue date:	07/11/1990
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
TASK-03-07.A, TASK-3-7.A, TASK-RR TAC-67427, NUDOCS 9007180303
Download: ML17261B092 (4)

Text

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR: 9007180303 DOC.DATE: 90/07/11 NOTARIZED:

NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas 6 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.

Project Directorate I-3

SUBJECT:

Responds to 900709 request for addi info re containment integrity insp.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR 2 ENCL 0 SIZE: TITLE: OR Submittal:

General Distribution DOCKET G 05000244 t D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244/RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: NRR/DET/ECMB 9H NRR/DST 8E2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS2 RES/DSIR/EIB EXTERNAL: LPDR NSIC COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-3 PD NRR/DOEA/OTSB11 NRR/DST/SELB 8D NRR/DST/SRXB 8E-8@M EG FILE 01 NRC PDR COPIES LTTR ENCL D D D NOTE TO ALL"RIDS" RECIPIENTS:

D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL e ill/////I///I//I/////

/I////1/I////////

ROCHESTER GAS wf~ai~owiie I'i RORY AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649.0001-July 11, 1990 TCtf PHONE ARKA cooK vie.546-2700 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-3 Washington, D.C.20555

Subject:

Containment Integrity Inspection R.E.Ginna Nuclear Power Plant Docket No.50-244

Reference:

July 9, 1990 NRC Request for Additional Information, (TAC No.67427),i

Dear Mr.Johnson:

In response to the NRC's July 9, 1990 request for additional information, RG&E is providing the following responses in an expeditious manner.RG&E does not believe that groundwater is entering the annular access area around containment from beneath containment, as suspected by NRC inspectors, but from behind the sheetpiling that form the retaining wall in the easternly quadrant of the intermediate building sub-basement.

Because this area is classified as a confined space, and is contaminated, the effort necessary to confirm this information is difficult.

Nonetheless, this major effort is underway.Preliminary results are expected by July 16, with detailed results expected by July 20.RG&E also does not expect that any degradation of containment structural members is occurring at this time.We have met all necessary surveillance testing requirements needed to conform to the Ginna Technical Specifications, including many Integrated Leak Rate Tests (ILRT)and tendon surveillance tests (reviewed in SEP Topic III-7.A).Results from the 1989 ILRT were excellent and the just-completed tendon testing confirmed that all lift-off tests met acceptance criteria, and all inspected tendon wires were in"as-new" condition.

RG&E will review the original structural design requirements of the containment and assess the impact of the recently determined groundwater level on the design.For structural details which are inaccessible due to location (high radiation area in the RHR room, or encased in rock or concrete)absolutely definitive conclusions may not be possible.However, 5'007180303 90'0711 ,PDR ADOCK 05000244 Q PDC our best engineering judgment will be used to provide reasonable

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11 J~'I i r assurance that the proper structural functions can be met.This approach is consistent with other, types of surveillance tests (e.g.MOVATS, testing in response to Generic Letter 89-10)where a duplication of post-accident functions cannot be achieved, but good judgment is used to extrapolate the ability to meet safety functions based on current available testing methodologies.

Any reasonably available information, whether NRC or industry generated, will be used to help us perform such correlations.

Because of the unique nature of the Ginna containment design, as discussed in our July ,9 telecon, RG&E proposes that.the NRC technical reviewers and RG&E personnel discuss our findings and conclusions at a mutually acceptable time, such as the end of the week of July 23, at the RG&E offices.Very truly yours, Robert C.Mecredy Division Manager Nuclear Production GJW/112 Attachment xc: Mr.Allen R.Johnson (Mail Stop 14D1)Project Directorate I-3 Washington, D.C.'0555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector