ML093030531
| ML093030531 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/17/2009 |
| From: | Borchardt R NRC/EDO |
| To: | Bonaca M Advisory Committee on Reactor Safeguards |
| doyle, D, NRR/DLR/RPB1, 415-3748 | |
| References | |
| EDATS: SECY-2009-0464, G20090605, LTR-09-0521, SECY-2009-0464, TAC ME2415 | |
| Download: ML093030531 (1) | |
Text
November 17, 2009 Dr. Mario V. Bonaca, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
RESPONSE TO THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS REPORT ON THE THREE-DIMENSIONAL FINITE ELEMENT ANALYSIS OF THE OYSTER CREEK NUCLEAR GENERATING STATION DRYWELL SHELL
Dear Dr. Bonaca:
During the 566th meeting of the Advisory Committee on Reactor Safeguards held October 8-10, 2009, the Committee completed its review of the three-dimensional finite element analysis (3-D FEA) of the Oyster Creek Nuclear Generating Station (Oyster Creek) drywell shell, as well as its review of the U.S. Nuclear Regulatory Commissions (NRCs) associated assessment. The Committees materials, metallurgy, and reactor fuels subcommittee also reviewed this matter during its meeting on September 23, 2009. The Committees review concluded that the analysis provides a modern, realistic, 3-D FEA that better quantifies the available safety margin for Oyster Creeks drywell shell, and confirms that the drywell shell complies with the current licensing basis for design basis accidents with margin. The Committee also concluded that the analysis was performed using good engineering practices and judgment and used conservatively biased realistic assumptions.
The NRC staff appreciates the Committees thorough review of both the 3-D FEA and the associated staff assessment. Additionally, the Committees letter of October 16, 2009, very clearly articulated both the complexities of this issue and the margins to safety that are maintained, which was of benefit to all stakeholders involved. The NRC staff recognizes the Committees commitment to safety and appreciates its continued support of the license renewal process.
Sincerely,
/RA Bruce S. Mallett for/
R. W. Borchardt Executive Director for Operations cc: Chairman Jaczko Commissioner Klein Commissioner Svinicki SECY
(Package) ML093030624; (Incoming) ML092940722, (Response) ML093030531
- concurred via e-mail OFFICE PM:DLR:RPB1 LA:DLR Tech Editor
- OGC*
NAME LRegner SFigueroa CHsu BHarris (NLO)
DATE 11/03/09 11/03/09 11/04/09 11/03/09 OFFICE BC:DLR:RPB1 D:DLR:NRR D:NRR EDO NAME BPham BHolian ELeeds (BBoger for)
RBorchardt (BMallett for)
DATE 11/03/09 11/09/09 11/10/09 11/17/09
Letter to Mario V. Bonaca from R. W. Borchardt dated November 17, 2009
SUBJECT:
RESPONSE TO THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS REPORT ON THE 3-DIMENSIONAL FINITE ELEMENT ANALYSIS OF THE OYSTER CREEK NUCLEAR GENERATING STATION DRYWELL SHELL DISTRIBUTION: G20090605/LTR-09-0521/EDATS : SECY-2009-0464 HARD COPY:
PUBLIC RidsEdoMailCenter Resource RidsNrrAdro Resource RidsNrrAdes Resource RidsNrrOd Resource RidsNrrMailCenter Resource RidsResOd RidsRgn1MailCenter Resource RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRer1 Resource RidsNrrDlrRer2 Resource RidsNrrDlrRerb Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDraAfpb Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource RidsOpaMail Resource A. Hiser B. Pham L. Regner D. Doyle D. Tifft, RI N. McNamara, RI D. Scenci, RI R. Conte, RI B. Harris, OGC