ML15224A255
| ML15224A255 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/14/1993 |
| From: | Wiens L Office of Nuclear Reactor Regulation |
| To: | Hampton J DUKE POWER CO. |
| References | |
| REF-GTECI-A-47, REF-GTECI-SY, TASK-A-47, TASK-OR GL-89-19, TAC-M74970, TAC-M74971, NUDOCS 9306180164 | |
| Download: ML15224A255 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 14, 1993 Docket Nos. 50-269, 50-270 and 50-287 Mr. J. W. Hampton Vice President, Oconee Site Duke Power Company P. 0. Box 1439 Seneca, South Carolina 29679
Dear Mr. Hampton:
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 REQUEST FOR ACTION RELATED TO RESOLUTION OF USI A-47 "SAFETY IMPLICATION OF CONTROL SYSTEMS IN LWR NUCLEAR POWER PLANTS" PURSUANT TO 10 CFR 50.54(f) GENERIC LETTER 89-19 (TACS M74970/M74971/M74971)
Generic Letter (GL) 89-19 was issued September 20, 1989, requesting action related to Unsolved Safety Issue A-47 concerning the safety implication of control system failures in LWRs. The staff concluded that all PWR plants should provide automatic steam generator overfill protection and establish plant procedures and technical specifications to ensure that the system remains available. You were to provide a response to the NRC outlining your intent to comply with the criteria of GL 89-19, or provide justification for not implementing the GL 89-19 recommendations. In a letter dated March 19, 1991, you described the system modification for providing steam generator overfill protection.
However, as stated in a letter dated September 24, 1991, the schedule for submitting technical specifications for the overfill protection system was deferred pending generic resolution of this issue for B&W plants.
By letter dated March 5, 1993, the Babcock & Wilcox Owners' Group (B&WOG) requested that the NRC staff consider a generic analysis of.steam generator overfill safety consequences in B&W plants as justification for resolution without the need to install automatic overfill protection. As a result of subsequent discussions with the B&WOG, by letter dated April 14, 1993, the B&WOG withdrew the analysis contained in the March 5, 1993, letter, and stated that resolution of the issues in GL 89-19 should be handled on a plant-specific basis.
On the basis of the above, you are requested to submit your response to GL 89-19 regarding the technical specifications and plant procedures within 45 days. This response is required pursuant to 10 CFR 50.54(f).
The technical specifications should include provisions to periodically 9306180164 930614 PDR ADOCK 05000269 PDPDR
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Mr. J. June 14, 1993 verify the operability of the overfill protection system with appropriate LCOs. The instrumentation should be demonstrated to be operable by the performance of a channel check, channel functional testing, and channel calibration, including setpoint verification.
If you have questions regarding this matter, contact me at (301) 504-1495.
Sincerely, ORIGINAL SIGNED BY:
L. A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation cc:
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Mr. J. W. Hampton Duke Power Company Oconee Nuclear Station cc:
Mr. A. V. Carr, Esquire Mr. M. E. Patrick Duke Power Company Compiance 422 South Church Street Duke Power Company Charlotte, North Carolina 28242-0001 Oconee Nuclear Site P. 0.-Box 1439 J. Michael McGarry, III, Esquire Seneca, South Carolina 29679 Winston and Strawn 1400 L Street, NW.
Mr. Alan R. Herdt, Chief Washington, DC 20005 Project Branch #3 U. S. Nuclear Regulatory Commission Mr. Robert B. Borsum 101 Marietta Street, NW. Suite 2900 Babcock & Wilcox Atlanta, Georgia 30323 Nuclear Power Division Suite 525 Ms. Karen E. Long 1700 Rockville Pike Assistant Attorney General Rockville, Maryland 20852 North Carolina Department of Justice Manager, LIS P. 0. Box 629 NUS Corporation Raleigh, North Carolina 27602 2650 McCormick Drive, 3rd Floor Clearwater, Florida 34619-1035 Mr. G. A. Copp Licensing -
ECO50 Senior Resident Inspector Duke Power Company U. S. Nuclear Regulatory Commission P. 0. Box 1006 Route 2, Box 610 Charlotte, North Carolina 28201-1006 Seneca, South Carolina 29678 Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, NW. Suite 2900 Atlanta, Georgia 30323 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health, South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603 County Supervisor of Oconee County Walhalla, South Carolina 29621