ML15112A577
| ML15112A577 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/09/1998 |
| From: | Labarge D NRC (Affiliation Not Assigned) |
| To: | Mccollum W DUKE POWER CO. |
| References | |
| TAC-M99297, TAC-M99298, TAC-M99299, NUDOCS 9802240240 | |
| Download: ML15112A577 (4) | |
Text
February 9, 1998 Mr. W. R. McCollum Vice President, Oconee Site Duke Energy Corporation P. 0. Box 1439 Seneca, SC 29679
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - (TAC NOS. M99297, M99298, AND M99299)
Dear Mr. McCollum:
During our review of your submittal dated July 15, 1997, to revise the Oconee Nuclear Station, Units 1, 2, and 3, Technical Specifications to incorporate modifications to the main steam line break detection and feedwater isolation circuitry, the staff has determined that additional information is necessary to complete its review. In order to maintain our review schedule, we request that you respond to the enclosed request for additional information within 60 days from the date of this letter.
Sincerely, ORIGINAL SIGNED BY:
David E. LaBarge, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/Il Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287
Enclosure:
As stated cc w/encl: See next page Distribution:
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-001 February 9, 1998 Mr. W. R. McCollum Vice President, Oconee Site Duke Energy Corporation P. 0. Box 1439 Seneca, SC 29679
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - (TAC NOS. M99297, M99298, AND M99299)
Dear Mr. McCollum:
During our review of your submittal dated July 15, 1997, to revise the Oconee Nuclear Station, Units 1, 2, and 3, Technical Specifications to incorporate modifications to the main steam line break detection and feedwater isolation circuitry, the staff has determined that additional information is necessary to complete its review. In order to maintain our review schedule, we request that you respond to the enclosed request for additional information within 60 days from the date of this letter.
Sincerely, David E. LaBarge, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/Il Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287
Enclosure:
As stated cc w/encl: See next page
Oconee Nuclear Station cc:
Mr. Paul R. Newton Mr. J. E. Burchfield Legal Department (PBO5E)
Compliance Manager Duke Energy Corporation Duke Energy Corporation 422 South Church Street Oconee Nuclear Site Charlotte, North Carolina 28242 P. 0. Box 1439 Seneca, South Carolina 29679 J. Michael McGarry, III, Esquire Winston and Strawn Ms. Karen E. Long 1400 L Street, NW.
Assistant Attorney General Washington, DC 20005 North Carolina Department of Justice Mr. Robert B. Borsum P. 0. Box 629 Framatome Technologies Raleigh, North Carolina 27602 Suite 525 1700 Rockville Pike L. A. Keller Rockville, Maryland 20852-1631 Manager - Nuclear Regulatory Licensing Manager, LIS Duke Energy Corporation NUS Corporation 526 South Church Street 2650 McCormick Drive, 3rd Floor Charlotte, North Carolina 28242-0001 Clearwater, Florida 34619-1035 Mr. Richard M. Fry, Director Senior Resident Inspector Division of Radiation Protection U. S. Nuclear Regulatory North Carolina Department of Commission Environment, Health, and 7812B Rochester Highway Natural Resources Seneca, South Carolina 29672 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Regional Administrator, Region II U. S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303 Max Batavia, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 County Supervisor of Oconee County Walhalla, South Carolina 29621
Request for Additional Information Main Steam Line Break Detection and Feedwater Isolation Systems In your July 15, 1997, proposed technical specification (TS) change to add TSs for the main steam line break (MSLB) and main feedwater (MFW) isolation circuitry, you propose to only include TSs for the MFW and MFW startup control valves and the MFW pump trip functions associated with MFW isolation. You further stated that no credit is taken for the MFW isolation function of the MFW block and startup feedwater block valves.
It is not clear to the staff that taking credit only for the control valves (main and startup) and the MFW pump trip meets the single failure criterion. If either the MFW control valve or the MFW startup control valve failed to close following an MSLB, tripping the MFW pump appears to allow the condensate and condensate booster pumps to continue to feed the depressurized (affected) steam generator through the idle MFW pumps. Bulletin 80-04 specifically identified that condensate flow should be considered as a potential energy source for continued feedwater addition following an MSLB.
Please identify how your system design addresses this concern without taking credit for the associated block valves. At a number of plants, an MFW pump trip results in closure signals to the MFW pump isolation valves that would prevent continued condensate flow to the affected steam generator. If a similar feature exists in your MFW pump design, please describe that associated feature.
If your MFW pump trip design does not include any associated pump isolation valve closure features, provide additional justification as to why the isolation function for the MFW block and startup block valves should not be included in the TSs in lieu of the MFW pump trip.
Enclosure