ML15117A250
| ML15117A250 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/03/1994 |
| From: | Wiens L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9408100203 | |
| Download: ML15117A250 (21) | |
Text
Docket Nos. 50-269, 50-2A August 3, 1994 A
Distribution and 50-287 W
W See attached page Licensee: Duke Power Company Facility: Oconee Nuclear Station, Units 1, 2, and 3
SUBJECT:
SUMMARY
OF JULY 21, 1994, MEETING WITH DUKE POWER COMPANY ON OCONEE SEISMIC EVENT LICENSING BASES ISSUES On July 21, 1994, NRC staff members met with representatives of Duke Power Company (DPC) at NRC Headquarters to discuss seismic issues relating to the Oconee licensing bases. The issues arose as a result of statements made in a letter from DPC to NRC dated May 25, 1994. Meeting attendees are included as. The meeting agenda is included as Enclosure 2 and copies of handouts provided during the meeting are included as Enclosure 3.
The two issues addressed at the meeting were the statements that the Oconee licensing bases do not postulate a single failure during a seismic event and that the licensing bases do not postulate a loss of offsite power and a seismic event occurring simultaneously. The licensee addressed the historical development of the Oconee licensing bases in these two areas and then described what the Oconee requirements were prior to 1979. A description of licensing activities after 1979, which related to seismic event assumptions and system design, was presented. The licensee then summarized what they had determined was the current seismic licensing bases for Oconee. The presentation concluded with a discussion of the DPC analysis of seismic vulnerabilities in the Oconee PRA, in which no risk-significant items had been identified relating to the two issues under discussion.
The NRC staff stated that there would be a caucus of the staff after the meeting, and that feedback from this caucus concerning their determination of the Oconee licensing bases would be provided to DPC separately. The meeting was then adjourned.
Original signed by:
Leonard A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Enclosures:
- 1. Meeting Attendees
- 2. Agenda
- 3. Handouts cc w/enclosures:
See next page
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DISTRIBUTION NRC & Local PDRs PDII-3 Reading File L. Wiens P. Harmon, RII C. Craig 0-17 G21 W. Russell/FMiraglia OGC 0-15 B18 R. Zimmerman 0-12 G18 S. Varga G. Lainas H. Berkow E. Jordan T-4 018 R. Carroll, Jr.
H. Ashar ACRS (10)
T-2 D32 L. Berry L. Plisco, EDO 0-12 E4 E. McCracken 0-8 D1 E. Weiss 0-7 E4 P. Chen 0-7 E23 S. Jones M. Caruso 0-8 E23 W. LeFave 0-8 D1 G. Hubbard 0-8 D1 F. Burrows 0-7 E4 F. Ashe 0-7 E4 H. Ornstein 0-4 A9 A. Gibson, RH T. Peebles, RH E. Mershcoff, RH
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UNITED STATES V
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 3, 1994 Docket Nos. 50-269, 50-270 and 50-287 Licensee: Duke Power Company Facility:
Oconee Nuclear Station, Units 1, 2, and 3
SUBJECT:
SUMMARY
OF JULY 21, 1994, MEETING WITH DUKE POWER COMPANY ON OCONEE SEISMIC EVENT LICENSING BASES ISSUES On July 21, 1994, NRC staff members met with representatives of Duke Power Company (DPC) at NRC Headquarters to discuss seismic issues relating to the Oconee licensing bases. The issues arose as a result of statements made in a letter from DPC to NRC dated May 25, 1994. Meeting attendees are included as. The meeting agenda is included as Enclosure 2 and copies of handouts provided during the meeting are included as Enclosure 3.
The two issues addressed at the meeting were the statements that the Oconee licensing bases do not postulate a single failure during a seismic event and that the licensing bases do not postulate a loss of offsite power and a seismic event occurring simultaneously. The licensee addressed the historical development of the Oconee licensing bases in these two areas and then described what the Oconee requirements were prior to 1979. A description of licensing activities after 1979, which related to seismic event assumptions and system design, was presented. The licensee then summarized what they had determined was the current seismic licensing bases for Oconee. The presentation concluded with a discussion of the DPC analysis of seismic vulnerabilities in the Oconee PRA, in which no risk-significant items had been identified relating to the two issues under discussion.
The NRC staff stated that there would be a caucus of the staff after the meeting, and that feedback from this caucus concerning their determination of the Oconee licensing bases would be provided to DPC separately. The meeting was then adjourned.
Leonard A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Enclosures:
- 1. Meeting Attendees
- 2. Agenda
- 3. Handouts cc w/enclosures:
See next page
Duke Power Company Oconee Nuclear Station cc:
A. V. Carr, Esquire Duke Power Company Mr. Steve Benesole 422 South Church Street Compliance Charlotte, North Carolina 28242-0001 Duke Power Company Oconee Nuclear Site J. Michael McGarry, III, Esquire P. 0. Box 1439 Winston and Strawn Seneca, South Carolina 29679 1400 L Street, NW.
Washington, DC 20005 Mr. Marvin Sinkule, Chief Project Branch #3 Mr. Robert B. Borsum U..S. Nuclear Regulatory Commission Babcock & Wilcox 101 Marietta Street, NW. Suite 2900 Nuclear Power Division Atlanta, Georgia 30323 Suite 525 1700 Rockville Pike Ms. Karen E. Long Rockville, Maryland 20852 Assistant Attorney General North Carolina Department of Manager, LIS Justice NUS Corporation P. 0. Box 629 2650 McCormick Drive, 3rd Floor Raleigh, North Carolina 27602 Clearwater, Florida 34619-1035 Mr. G. A. Copp Senior Resident Inspector Licensing - EC050 U. S. Nuclear Regulatory Commission Duke Power Company Route 2, Box 610 526 South Church Street Seneca, South Carolina 29678 Charlotte, North Carolina 28242-0001 Regional Administrator, Region.II Dayne H. Brown, Director U. S. Nuclear Regulatory Commission Division of Radiation Protection 101 Marietta Street, NW. Suite 2900 North Carolina Department of Atlanta, Georgia 30323 Environment, Health and Natural Resources Max Batavia, Chief P. 0. Box 27687 Bureau of Radiological Health Raleigh, North Carolina 27611-7687 South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 County Supervisor of Oconee County Walhalla, South Carolina 29621 Mr. J. W. Hampton Vice President, Oconee Site Duke Power Company P.O. Box 1439 Seneca, South Carolina 27679
MEETING ATTENDEES DUKE POWER SEISMIC LICENSING BASIS July 21, 1994 NAME ORGANIZATION Len Wiens NRC/NRR/PDII-3 Herb Berkow NRC/NRR/PDII-3 Conrad McCracken NRC/NRR/SPLB Eric Weiss NRC/NRR/EELB Hans Ashar NRC/NRR/ECGB Pei-Ying Chen NRC/NRR/EMEB Steve Jones NRC/NRR/SPLB Mark Caruso NRC/NRR/SRXB Bill LeFave NRC/NRR/SPLB George Hubbard NRC/NRR/SPLB Fred Burrows NRC/NRR/EELB Frank Ashe NRC/NRR/EELB Gus Lainas NRR/NRR/ADRII Hal Ornstein NRC/AEOD Michael Bailey Duke/ONS/Regulatory Compliance Steve Nader Duke/ONS/Mechanical Systems Engineering Rounette Kellahan Duke/ONS/Mechanical Systems Engineering Joe M. Davis Duke/ONS/Engineering Manager J. W. Hampton Duke/ONS/VP Bryan Dolan Duke/ONS/Safety Assurance Manager Steve Benesole Duke/ONS/Compliance Manager David B. Coyle Duke/ONS/Mechanical Systems Engineer Manager Albert F. Gibson NRC/Rh/Director Division of Reactor Safety Paul Harmon NRC/RII/Oconee Resident Inspector T. A. Peebles NRC/R II
ENCLOSURE 2 AGENDA o OCONEE LICENSING HISTORY o ORIGINAL REQUIREMENTS o POST TMI REQUIREMENTS o
SUMMARY
o SAFETY SIGNIFICANCE
DUKE/NRC MEETING RELATING TO OCONEE SEISMIC EVENT LICENSING BASES ISSUES JULY 21, 1994
HISTORY OF LICENSING BASES RELATIVE TO SEISMIC/
SINGLE FAILURE/LOOP o OCONEE LICENSED TO DRAFT ATOMIC ENERGY COMMISSION GENERAL DESIGN CRITERIA o GL 81-14 WAS ISSUED TO ASSURE THAT PLANTS MEET GENERAL DESIGN CRITERIA 2 AND 34 FOR EMERGENCY FEEDWATER SYSTEM
SUMMARY
OF ORIGINAL DESIGN REQUIREMENTS o SEISMIC DESIGN o SINGLE FAILURE REQUIREMENTS o OFF-SITE/ON-SITE POWER REQUIREMENTS o POSTULATION OF PIPE BREAK REQUIREMENTS
SEISMIC DESIGN REQUIREMENTS o CRITERION 2 "PERFORMANCE STANDARDS" o FSAR 3.2.1.2 "COMPONENTS AND SYSTEMS" o FSAR 3.7.3.9 "INTERACTION OF PIPING WITH PIPING DESIGNED FOR SEISMIC CONDITIONS"
SINGLE FAILURE REQUIREMENTS o OCONEE CRITERION 10 "PROTECTION SYSTEM REDUNDANCY AND INDEPENDENCE" o CRITERION 39 "EMERGENCY POWER FOR ENGINEERED SAFETY FEATURES" o CRITERION 41 "ENGINEERED SAFETY FEATURES PERFORMANCE CAPABILITY" o NOT LICENSED TO GENERAL DESIGN CRITERIA 34 "RESIDUAL HEAT REMOVAL"
SINGLE FAILURE REQUIREMENTS (continued) o "REDUNDANCY WITHIN THE STEAM CONVERSION SYSTEM IN SUCH THAT THE HEAT REMOVAL ADEQUACY OF THIS SYSTEM IS NOT IMPAIRED BY SINGLE FAILURES OF COMPONENTS, EQUIPMENT OR PIPING" UI SER PAGE 62)
OFF-SITE/ON-SITE POWER REQUIREMENTS o CRITERION 6 "REACTOR CORE DESIGN" o CRITERION 24 "ELECTRICAL POWER FOR PROTECTIVE SYSTEM" 0 CRITERION 39 "EMERGENCY POWER FOR ENGINEERED SAFETY FEATURES"
POSTULATION OF PIPE BREAK REQUIREMENTS o HIGH ENERGY LINE BREAK o REVIEW OF FLOODING POTENTIAL o SEISMIC INDUCED PIPE BREAK WAS NOT POSTULATED
SUMMARY
OF LICENSING REQUIREMENTS (PRE 1979) o SAFETY RELATED REDUNDANCY IN ACCIDENT MITIGATION SYSTEMS o DIVERSITY DESIGNED INTO SECONDARY SIDE OF PLANT o SEISMIC DESIGN WAS A CRITERIA FOR DESIGN OF PIPING, COMPONENTS AND STRUCTURES o SPECIFIC PIPE BREAKS ANALYZED 0 POWER REQUIREMENTS
0 0
GENERIC LETTER 81-14 o EMERGENCY FEEDWATER SYSTEM SHOULD BE IN CONFORMANCE WITH GENERAL DESIGN CRITERIA 2 AND 34 o DUKE IDENTIFIED SEVERAL SEISMIC DEFICIENCIES IN EMERGENCY FEEDWATER SYSTEM AND PROPOSED STANDBY SHUTDOWN FACILITY AS A SUITABLE ALTERNATE o NRC STATED GENERAL DESIGN CRITERIA 2 AND 34 OUTSIDE OCONEE CURRENT LICENSING BASES AND CONSIDERED BACKFIT
0 S
GENERIC LETTER 81-14 (continued) o NRC ACCEPTED DUKE DESIGN AND DID NOT PURSUE BACKFIT DUE TO DIVERSITY OF SYSTEMS
CURRENT SEISMIC LICENSING BASES o LOSS OF COOLANT ACCIDENT o CONCURRENT LOSS OF OFFSITE POWER WITH SINGLE FAILURE ACTION FAILURES ASSUMED o CONCURRENT SEISMIC EVENT OR INDEPENDENT PIPE BREAK NOT POSTULATED o LOSS OF OFF-SITE POWER o INITIATOR OF LOSS OF OFF SITE POWER NOT DESCRIBED
CURRENT SEISMIC LICENSING BASES (continued) o SINGLE ACTIVE FAILURE POSTULATED o PIPE FAILURES NOT DEEMED CREDIBLE, THEREFORE, NOT POSTULATED o SEISMIC EVENT o NOT REVIEWED AS AN ACCIDENT o DESIGN CRITERIA FOR PIPING, EQUIPMENT AND STRUCTURES USED FOR MITIGATION OR PREVENTION OF ACCIDENTS OR SAFE SHUTDOWN OF PLANT
CURRENT SEISMIC. LICENSING BASES (continued) o FAILURE OF PIPING AND ASSOCIATED BOUNDARY VALVE NOT DEEMED CREDIBLE AND NOT POSTULATED
SAFETY SIGNIFICANCE