ML043380105

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Summary of Meeting with Duke Energy Corporation Regarding License Amendment Request for Digital Upgrade or Rps/Esps of Oconee
ML043380105
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 01/03/2005
From: Olshan L
NRC/NRR/DLPM/LPD2
To:
NRC/NRR/DLPM
Olshan L N, NRR/DLPM, 415-1419
References
TAC MB8086, TAC MB8087, TAC MB8088
Download: ML043380105 (4)


Text

January 3, 2005 LICENSEE: Duke Energy Corporation FACILITY: Oconee Nuclear Station, Units 1, 2, and 3

SUBJECT:

SUMMARY

OF NOVEMBER 17, 2004, MEETING TO DISCUSS LICENSE AMENDMENT REQUEST FOR DIGITAL UPGRADE OF RPS/ESPS (TAC NOS.

MB8086, MB8087, AND MB8088)

On November 17, 2004, a Category 1 meeting was held between the Nuclear Regulatory Commission (NRC) and representatives from Duke Energy Corporation (the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss a license amendment request that the licensee will be submitting to accommodate the digital upgrade of the Oconee Reactor Protective System/Engineered Safeguards Protective System (RPS/ESPS). A list of attendees is provided in Attachment 1. are the slides presented by the licensee during the meeting.

By letter dated March 20, 2003, the licensee submitted a defense-in-depth and diversity (D3) analysis to support the digital upgrade of RPS/ESPS. In the event of a common mode failure of the digital RPS/ESPS, the D3 analysis concluded that all transients and accidents, with the exception of the large break loss-of-coolant (LOCA) accident, could be adequately mitigated assuming reasonable operator actions. The D3 analysis took credit for leakage detection systems to eliminate consideration of the large break LOCA. Prior to the meeting, the NRC staff had informed the licensee that this application of leakage detection systems could not be approved at this time. In addition, the Electric Power Research Institute (EPRI) is preparing a risk-informed methodology that may be able to demonstrate that the diverse low-pressure injection actuation system (DLPIAS) does not have to be installed. However, it is not certain that the NRC staff will accept the leakage-detection-system approach or the EPRI methodology prior to the planned implementation of the digital RPS/ESPS modification, which is scheduled to begin in Fall 2006. Therefore, the licensee is designing a DLPIAS.

The licensee presented the design requirements that the licensee believes are appropriate for the DLPIAS. These design requirements are listed on pages 9, 10, and 11 of Attachment 2.

The NRC staff concurred that these design requirements were appropriate for the DLPIAS.

/RA/

Leonard N. Olshan, Senior Project Manager Project Directorate II-1 Division of Project Licensing Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-0287 Attachments: As stated cc w/atts: See next page

LICENSEE: Duke Energy Corporation FACILITY: Oconee Nuclear Station, Units 1, 2, and 3

SUBJECT:

SUMMARY

OF NOVEMBER 17, 2004, MEETING TO DISCUSS LICENSE AMENDMENT REQUEST FOR DIGITAL UPGRADE OF RPS/ESPS (TAC NOS.

MB8086, MB8087, AND MB8088)

On November 17, 2004, a Category 1 meeting was held between the Nuclear Regulatory Commission (NRC) and representatives from Duke Energy Corporation (the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss a license amendment request that the licensee will be submitting to accommodate the digital upgrade of the Oconee Reactor Protective System/Engineered Safeguards Protective System (RPS/ESPS). A list of attendees is provided in Attachment 1. are the slides presented by the licensee during the meeting.

By letter dated March 20, 2003, the licensee submitted a defense-in-depth and diversity (D3) analysis to support the digital upgrade of RPS/ESPS. In the event of a common mode failure of the digital RPS/ESPS, the D3 analysis concluded that all transients and accidents, with the exception of the large break loss-of-coolant (LOCA) accident, could be adequately mitigated assuming reasonable operator actions. The D3 analysis took credit for leakage detection systems to eliminate consideration of the large break LOCA. Prior to the meeting, the NRC staff had informed the licensee that this application of leakage detection systems could not be approved at this time. In addition, the Electric Power Research Institute (EPRI) is preparing a risk-informed methodology that may be able to demonstrate that the diverse low-pressure injection actuation system (DLPIAS) does not have to be installed. However, it is not certain that the NRC staff will accept the leakage-detection-system approach or the EPRI methodology prior to the planned implementation of the digital RPS/ESPS modification, which is scheduled to begin in Fall 2006. Therefore, the licensee is designing a DLPIAS.

The licensee presented the design requirements that the licensee believes are appropriate for the DLPIAS. These design requirements are listed on pages 9, 10, and 11 of Attachment 2.

The NRC staff concurred that these design requirements were appropriate for the DLPIAS.

/RA/

Leonard N. Olshan, Senior Project Manager Project Directorate II-1 Division of Project Licensing Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-0287 Attachments: As stated cc w/atts: See next page Distribution:

PUBLIC RidsAcrsAcnwMailCenter CHawes RMartin PDIV-1 R/F RidsNrrDlpm CDoutt PRebstock LOshan RidsNrrDlpmLPDII(EHackett) PLoeser CSchulten RidsOgcRp RidsNrrDlpmLPDII-1(JNakoski) EMarinos MStutzke JDixon-Herrity RidsRgn2MailCenter Accession Number: ML043380105 OFFICE PDII-1/PM PDII-1/LA EEIB/SC PDII-1/SC NAME LOlshan CHawes EMarinos JNakoski DATE 1/3/05 12/20/04 12/6/04 1/3/05 OFFICIAL RECORD COPY

LIST OF ATTENDEES MEETING TO DISCUSS LICENSE AMENDMENT REQUEST FOR DIGITAL UPGRADE OF RPS/ESPS NOVEMBER 17, 2004 NRC C. Doutt P. Loeser E. Marinos R. Martin L. Olshan P. Rebstock C. Schulten M. Stutzke DUKE R. Cornett G. Davenport M. Miller D. Repko B. Shingleton B. Thomas Other P. Berry, Framatome P. Liddle, Framatome J. Mauck, Framatome C. Brinkman, Westinghouse R. Torok, Electric Power Research Institute Attachment 1

Oconee Nuclear Station, Units 1, 2, and 3 cc:

Ms. Lisa F. Vaughn Ms. Karen E. Long Duke Energy Corporation Assistant Attorney General Mail Code - PB05E NC Department of Justice 422 S. Church St. P.O. Box 629 P.O. Box 1244 Raleigh, NC 27602 Charlotte, NC 28201-1244 Mr. R. L. Gill, Jr.

Ms. Anne W. Cottingham, Esq. Manager - Nuclear Regulatory Winston and Strawn Issues and Industry Affairs 1400 L St, NW Duke Energy Corporation Washington, DC 20005 526 S. Church St.

Mail Stop EC05P Manager, LIS Charlotte, NC 28202 NUS Corporation 2650 McCormick Dr., 3rd Floor Mr. Richard M. Fry, Director Clearwater, FL 34619-1035 Division of Radiation Protection NC Dept of Environment, Health, & Natural Senior Resident Inspector Resources U.S. Nuclear Regulatory Commission 3825 Barrett Dr.

7812B Rochester Highway Raleigh, NC 27609-7721 Seneca, SC 29672 Mr. Peter R. Harden, IV Mr. Henry Porter, Director VP-Customer Relations and Sales Division of Radioactive Waste Management Westinghouse Electric Company Bureau of Land and Waste Management 6000 Fairview Road Dept. of Health and Env. Control 12th Floor 2600 Bull St. Charlotte, NC 28210 Columbia, SC 29201-1708 Mr. Henry Barron Mr. Michael A. Schoppman Group Vice President, Nuclear Generation Framatome ANP and Chief Nuclear Officer 1911 North Ft. Myer Dr. P.O. Box 1006-EC07H Suite 705 Charlotte, NC 28201-1006 Rosslyn, VA 22209 Mr. Ronald A. Jones Mr. B. G. Davenport Vice President, Oconee Site Regulatory Compliance Manager Duke Energy Corporation Oconee Nuclear Site 7800 Rochester Highway Duke Energy Corporation Seneca, SC 29672 ON03RC 7800 Rochester Highway Seneca, SC 29672