ML14224A243

July 31, 2014, Summary of Public Meeting, Oconee

ML14224A243
Person / Time
Site:	Oconee
Issue date:	08/12/2014
From:	Gerald Mccoy NRC/RGN-II/DRP/RPB1
To:	Batson S Duke Energy Carolinas
References
Download: ML14224A243 (7)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 August 12, 2014 Mr. Scott Batson Site Vice President Duke Energy Carolinas, LLC Oconee Nuclear Station 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

PUBLIC MEETING

SUMMARY

- OCONEE NUCLEAR STATION -

DOCKET NO. 50-269

Dear Mr. Batson:

This refers to the Regulatory Conference conducted at NRC Region II office on July 31, 2014, concerning the preliminary Greater than Green finding for Oconee Nuclear Station Unit 1, as documented in NRC inspection report 05000269/2014011. The meeting purpose was to provide an opportunity for you to explain your position regarding the preliminary finding and to address the failure to promptly identify and correct a condition adverse to quality as required by 10 CFR 50, Appendix B, Criterion XVI. Enclosed are a list of attendees and a copy of the additional slide you presented at the meeting. The main set of presentation slides is available in the NRCs Agencywide Documents Access and Management System under accession numbers ML14211A213 and ML14211A216.

In accordance with Title 10 of the Code of Federal Regulations (CFR) 2.390 of the NRC's Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room (PDR) or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Should you have any questions concerning this meeting, please contact me at 404-997-4551.

Sincerely,

/RA/

Gerald J. McCoy, Chief Reactor Projects Branch 1 Division of Reactor Projects

Enclosures:

1. List of Attendees

2. Handout - Additional Slide Presented by Licensee cc: Distribution via Listserv

August 12, 2014 Mr. Scott Batson Site Vice President Duke Energy Carolinas, LLC Oconee Nuclear Station 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

PUBLIC MEETING

SUMMARY

- OCONEE NUCLEAR STATION - DOCKET NO.

50-269

Dear Mr. Batson:

This refers to the Regulatory Conference conducted at NRC Region II office on July 31, 2014, concerning the preliminary Greater than Green finding for Oconee Nuclear Station Unit 1, as documented in NRC inspection report 05000269/2014011. The meeting purpose was to provide an opportunity for you to explain your position regarding the preliminary finding and to address the failure to promptly identify and correct a condition adverse to quality as required by 10 CFR 50, Appendix B, Criterion XVI.

Enclosed are a list of attendees and a copy of the additional slide you presented at the meeting. The main set of presentation slides is available in the NRCs Agencywide Documents Access and Management System under accession numbers ML14211A213 and ML14211A216.

In accordance with Title 10 of the Code of Federal Regulations (CFR) 2.390 of the NRC's Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room (PDR) or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Should you have any questions concerning this meeting, please contact me at 404-997-4551.

Sincerely,

/RA/

Gerald J. McCoy, Chief Reactor Projects Branch 1 Division of Reactor Projects

Enclosures:

1. List of Attendees

2. Handout - Additional Slide Presented by Licensee cc: Distribution via Listserv Distribution:

L. Douglas, EICS Public Document Room RIDSNRRDIRS RidsNrrPMOconee Resource Program Office Project Manager NRC Resident Inspectors Responsible Branch Chief PUBLICLY AVAILABLE NON-PUBLICLY AVAILABLE SENSITIVE NON-SENSITIVE ADAMS:

Yes ACCESSION NUMBER:_________________________

SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRP RII:DRP SIGNATURE

/AMR4/

/GJM1/

NAME ARuh GMcCoy DATE 8/12/2014 8/12/2014 E-MAIL COPY?

YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME:

G:\\DRPII\\RPB1\\OCONEE\\MEETINGS\\OCO REG CONF

SUMMARY

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• CRP (6E-04) x CCDP represents increase in risk with the following assumptions:

• Leak is assumed to exist for 1 year

• Large uncertainty in crack length applied

• Through-wall leak in HPI pipe is a given condition

• Bounding stress applied to grow crack

• No repair of leak for one year

• Proposed adjustments

[CRP (6E-04) x CCDP x fi x f2] 1(1 year) = change in CDF = <<1 OE-7 Iyr

• fi: HPI Thru wall crack is not identified and not repaired is <1 E-02

• f2: bounding stresses are expected to occur is <1 E-02 Result: Increase in CDF in this approach is very low safety significance For Information Only