ML16152A374
| ML16152A374 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 09/12/1984 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Tucker H DUKE POWER CO. |
| References | |
| NUDOCS 8410310689 | |
| Download: ML16152A374 (5) | |
Text
SEP I1. 19 FFIL c Duke Power Company C py ATTN:
Mr. H. B. Tucker, Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:
SUBJECT:
MEETING
SUMMARY
- DOCKET NOS. 50-269, 50-270, 50-287, 50-369, 50-370, AND 50-413 This letter refers to the meeting conducted at your request in the Region II Office on August 15, 1984.
The meeting centered on discussions of the Standby Shutdown Facility (SSF) authorized for operation by NRC License Nos.
NPF-9 and NPF-17 for McGuire Units 1 and 2, and NPF-24 for Catawba Unit 1; the Oconee SSF has been built, but is not yet operational.
Enclosed is a summary of the meeting topics.
Our concerns regarding the operation of SSF and its intent of satisfying the requirements of Appendix R to 10 CFR Part 50 and 10 CFR Part 73 were expressed to you at the meeting and your positive response to our concerns is appreciated.
It is our opinion that the meeting was beneficial and has provided for a better understanding of the SSF design and its function.
In accordance with Section 2.790 of NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and enclosure will be placed in the NRC's Public Document Room.
Should you have any questions regarding this matter, we will be pleased to discuss them.
Sincerely James P. O'Reilly Regional Administrator
Enclosure:
Meeting Summary cc w/encl:
M. D. McIntosh, McGuire Station Manager M. S. Tuckman, Oconee Station Manager R. L. Dick, Vice President - Construction J. W. Hampton, Catawba Station Manager 8410310689 840912 PDR ADOCK 05000269 F
SEP 12 1984 ENCLOSURE MEETING
SUMMARY
Licensee:
Duke Power Company Facilities:
Catawba, McGuire, and Oconee Docket Nos.:
50-413, 50-369, 50-370, 50-269, 50-270, and 50-287 License Nos.:
NPF-24, NPF-9, NPF-17, DPR-38, DPR-47, and DPR-55
SUBJECT:
DESIGN AND OPERATION OF THE STANDBY SHUTDOWN FACILITY AS IT RELATES TO 10 CFR 50, APPENDIX R, AND 10 CFR 73 A meeting was held on August 15, 1984, to discuss the design and operation of the Standby Shutdown Facility, as it relates to 10 CFR Part 50, Appendix R, Fire Protection, and 10 CFR Part 73, Physical Protection.
The Duke Power Company requested an opportunity to make a presentation on the Standby Shutdown Facility design concept and its system's functional description.
This was presented to the NRC staff on August 15, 1984.
The meeting summary notes are described below.
- a. SSF Historical Background and Design The Standby Shutdown Facility (SSF) concept was developed from a Duke task force study, formed in 1977, to review the Browns Ferry fire, Oconee turbine building flood and security issues. This concept was then presented to the NRC staff on January 18, 1978, for the Oconee Nuclear Station and on March 23, 1978, for the McGuire Nuclear Station. The NRC staff's review of the SSF design followed with their findings were reported in Safety Evaluation Reports (SERs) dated April 1983, February 1983, and July 1984, for the respective facilities of Oconee, McGuire, and Catawba.
The SSF is designed to provide an alternate and independent means to achieve and maintain hot standby conditions for the Duke facilities.
Furthermore, it was designed to mitigate consequences of a fire or sabotage events non-concurrent with other design basis events. For the Catawba and McGuire facilities, the SSF structure and its systems are not safety-related, except where the interface to existing plant requires it to be.
SEP 12 1984 Duke Power Company 2
Duke discussed SSF fire design criteria as related to the Appendix R requirements and NRC BTP-9.5-1. The associated circuit review was also discussed in which the licensee has stated that under a better understand ing of its definition, this subject matter turned out to be of a larger scope than earlier anticipated and led to a re-review of the McGuire design in March 1984.
- b.
SSF Functional Description and Operation To achieve and maintain hot standby conditions of the affected unit, the SSF has the capability by independent means of providing primary and secondary system volume and pressure control.
The SSF electrical loads are supplied by its diesel generator; it is independent of onsite emergency diesel generators.
Duke described the various systems including the process required of electrical power transfer/separation from the Class 1E Trains "A" and "B" for activation of the SSF. The SSF can be manually activated and operated in ten minutes. The ten minute time frame was based on reactor coolant pump seal degradation from having no seal water supply. However, based on new pump vendor studies, the seals are expected to last much longer. The licensee also discussed the adequacy of the SSF standby makeup pump.
- c.
Summary and Comments In summary, Duke has described the design and operation of the SSF. The SSF can take the unit down to hot standby condition and maintain it for a considerable time to effect repairs of cold shutdown equipment.
The NRC expressed concern on the lack of licensee controls associated with the operation of McGuire SSF. The licensee has stated that they expect to submit the proposed McGuire SSF Technical Specifications in September 1984.
SEP 1 2 1984 ATTACHMENT ATTENDANCE LIST Attendance at the Duke-NRC meeting on August 15,
- 1984, at the NRC's Region II Office included:
Duke Power Company H. B. Tucker, Vice President, Nuclear Production K. S. Canady, Manager, Nuclear Engineering Services T. C. McMeekin, Chief Engineer, Electrical Engineering R. W. Revels, Engineer, Design Engineering D. W. Murdock, Engineer, Design Engineering H. L. Davenport, Engineer, Design Engineering R. L. Dobson, Design Engineering B. F. Caldwell, Security and Fire Protection R. G. Morgan, Nuclear Operations D. B. Adkins, Security J. R. Hendricks, Design Engineering NRC James P. O'Reilly, Regional Administrator R. C. Lewis, Director, Division of Reactor Projects (DRP)
J. A. Olshinski, Director, Division of Reactor Safety (DRS)
J, P. Stohr, Director, Division of Reactor Safety and Safeguards (DRSS)
C. 0. Thomas, Chief, Standardization and Special Projects Branch, NRR K. N. Jabbour, Catawba Licensing Project Manager, NRR H. Nicolaras, Oconee Licensing Project Manager, NRR
- 0. D. Parr, Chief, Auxiliary Systems Branch, NRR R. L. Ferguson, Chemical Engineering Branch, NRR N. Fioravante, Auxiliary Systems Branch, NRR C. E. Gaskin, Division of Safeguards, NMSS H. C. Dance, Chief, Reactor Projects Branch 2, DRP V. L. Brownlee, Chief, Reactor Projects Section (RPS) 2A, DRP K. P. Barr, Chief, Nuclear Materials Safety and Safeguards Branch, DRSS D. R. McGuire, Chief, Physical Security Section, DRSS W. T. Orders, Senior Resident Inspector at McGuire, RPS 2A, DRP A. J. Ignatonis, Project Engineer, RPS 2A, DRP Other Region II Personnel
SEP 12 1984 Duke Power Company 2
bcc w/encl:
NRC Resident Inspector G. Johnson, ELD Document Control Desk State of North Carolina James L. Kelley, Chairman Atomic Safety and Licensing Board Dr. Paul W. Purdom Administrative Judge Dr. Richard F. Foster Administrative Judge Robert Guild, Esq.
Palmetto Alliance Jesse L. Riley Carolina Environmental Study Group RII RII RI R
Algnatonis:sa H
VBrownlee R ance R Lewis 09/S/84 J
09/S7/84 09/1 /84 09/# /84