Letter Sequence Meeting |
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MONTHYEARML0415902732004-06-0707 June 2004
TIA 04-02 Request for Technical Assistance Re Degraded Voltage Protection at D. C. Cook
Project stage: Request
ML0429201582004-11-0404 November 2004
Opportunity to Provide Information Regarding Request for Technical Assistance (TIA)2004-02, Degraded Voltage Protection at D.C. Cook.
Project stage: Other
ML0433403052004-11-30030 November 2004
Notice of Meeting with Indiana Michigan Power Company to Discuss the Degraded Voltage Protection Design at the Donald C. Cook Nuclear Plant
Project stage: Request
ML0435000152004-12-10010 December 2004
Degraded Voltage Protection at Plant
Project stage: Other
ML0434400872004-12-16016 December 2004
Summary of Meeting Held December 8, 2004, to Discuss the Degraded Voltage Protection Design
Project stage: Meeting
ML0434803502005-02-28028 February 2005
Response to Task Interface Agreement (TIA 2004-02), Request for Protection
Project stage: Other
2004-12-10
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[Table view] |
Text
December 16, 2004 LICENSEE: Indiana Michigan Power Company FACILITY: Donald C. Cook Nuclear Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF MEETING ON DECEMBER 8, 2004, TO DISCUSS THE DEGRADED VOLTAGE PROTECTION DESIGN AT DONALD C. COOK NUCLEAR PLANT (TAC NOS. MC3428 AND MC3429)
On December 8, 2004, members of the U.S. Nuclear Regulatory Commission (NRC) staff met with Indiana Michigan Power Company (IM, the licensee), representatives at NRC Headquarters, Two White Flint North, 11545 Rockville Pike, Rockville, MD. The meeting was also audio-conferenced with licensee and NRC staff at Donald C. Cook Nuclear Plant (CNP).
The meeting was a Category 1 public meeting; however, no members of the public were present.
The purpose of the meeting was to allow the licensee to present their answers to questions posed by the NRC staff in a letter dated November 4, 2004 (ML042920158). During a Region III inspection last year, inspectors noted that automatic degraded voltage protection is bypassed (1) during normal operation and (2) during the first 30 seconds of a design-basis event. The NRC staff preliminarily concluded that the degraded voltage protection design does not provide adequate safety and is not in compliance with the technical specification (TS) requirement. The NRC staff asked the licensee to address (1) how the existing degraded voltage protection at CNP adequately assures plant safety, (2) how CNP meets NRC staff position MPA B-23, and (3) how CNP is in compliance with TS 3.3.2.1.
The meeting agenda was provided with the meeting notice (ML043340305, Meeting No.
2004-0708). The licensees presentation slides were placed in ADAMS following the meeting (ML043440089). A list of attendees is enclosed.
The licensees presentation included information on (1) the differences between the electrical distribution system arrangement at CNP and the arrangement generally found in the industry, (2) the implications of the electrical distribution arrangement for the degraded voltage protection design, (3) the response of the electrical system to various voltage conditions on the grid, and (4) the licensee's understanding of how CNP complies with the staff position and TS requirements. The licensee and NRC staff conducted a vigorous dialogue of the issues. No regulatory decisions were made. Following the presentation, the licensee stated that they intended to provide a written response to the questions in the staff's November 4, 2004, letter, by December 10, 2004. The NRC staff thanked the licensee for their presentation and informed them that the information provided would be considered in reaching a regulatory determination.
/RA/
Carl F. Lyon, Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosure:
Attendance List cc w/encl: See next page
The licensees presentation included information on (1) the differences between the electrical distribution system arrangement at CNP and the arrangement generally found in the industry, (2) the implications of the electrical distribution arrangement for the degraded voltage protection design, (3) the response of the electrical system to various voltage conditions on the grid, and (4) the licensee's understanding of how CNP complies with the staff position and Technical Specification requirements. The licensee and NRC staff conducted a vigorous dialogue of the issues. No regulatory decisions were made. Following the presentation, the licensee stated that they intended to provide a written response to the questions in the staff's November 4, 2004, letter by December 10. The NRC staff thanked the licensee for their presentation and informed them that the information provided would be considered in reaching a regulatory determination.
/RA/
Carl F. Lyon, Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosure:
Attendance List cc w/encl: See next page DISTRIBUTION:
PUBLIC PDIII-1 R/F LMarsh/JLyons JLara, RIII FLyon THarris DWeaver, EDO WRuland EDuncan, RIII TMensah, NRR Comm Analyst MKotzalas OGC ACRS AGill SRay TKoshy LTrocine LRaghavan BSheron INetzel RJenkins JCalvo ADAMS Accession Number: ML043440087 *Previously concurred OFFICE PDIII-1/PM PDIII-1/LA PDIII-1/SC NAME FLyon THarris* MKotzalas DATE 12/16/04 12/16/04 12/16/04 OFFICIAL RECORD COPY
ATTENDANCE LIST NRC MEETING WITH INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT DEGRADED VOLTAGE PROTECTION DECEMBER 8, 2004 J. Zwolinski, IM A. Gill, NRC D. Fadel, IM S. Ray, NRC G. Kilpatrick, IM T. Koshy, NRC B. Lord, IM L. Trocine, NRC P. Schoepf, IM M. Kotzalas, NRC M. Scarpello, IM L. Raghavan (part-time), NRC C. Fleming, Winston and Strawn B. Sheron (part-time), NRC M. Finissi (audio), IM F. Lyon, NRC J. Waters (audio), IM W. Ruland, NRC R. Jenkins, NRC L. Marsh, NRC J. Calvo, NRC I. Netzel (audio), NRC J. Lara, NRC
