ML14192A263
| ML14192A263 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/26/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Jackie Jones CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 8111040610 | |
| Download: ML14192A263 (3) | |
Text
DISTRIBUTION Docket NRC PDR L PDR OCT 2 6 1981 TERA Docket No. 50-261 NSIC ORB#1 Rdg DEisenhut OELD Mr. J. A. Jones 0
IE-3 Senior Vice President ACRS-1O Carolina Power and Light Company JHeltemes 336 Fayetteville Street Cc SVarga Raleigh, North Carolina 27602 OCT2 T 1981t WRoss
- s. O J CParrish
Dear Mr. Jones:
OGC Gray File By letters dated January 19 and March 11, 1981 Carnd Light Company requested an exemption from the requirements of Secton.6 of Appendix R to 10 CFR 50 "Oil Collection System for Reactor Coolant Pump" for Robinson-2.
This subject was discussed further at a meeting between.the staff and represent=
atives of Carolina Power and Light Company on July 28, 1981.
At the conclusion of this meeting the staff requested that additional information be provided to enable us to make a decision on the exemption request.
During a subsequent telephone conlbration between the Robinson-a Project Manager and88avid Stadler of your staff, Mr. Stadler requested that the staff's concerns and requests be clarified. In response to this request, I am providing the
'1ollowitg information which soummainiizns.the staffts current understanding of this matter and descI#bes the areas where additional information is needed.
Section III.0, "Oil Collection System for Reactor Coolant Pump" Our initial review of this request assumed a fire resulting from 10-15 gallons of oil remaining in oil soaked insulation after an RCP oil leak. Your exemption request indicated that the bulk of the oil would be drained 4way via the sumpp drain. During the July 28, 1981 meeting, you stated that your analysis assumed that all the oil contained in one pump was consumed in a fire at the pump loca tion. You also stated that your analysis had developed temperature profiles in the immediate and adjhcent areas of the pump.
Provide the results of your analysis 4,or this event. Include the amount of oil consumed, the fire dUration, temperature profiles calculated, essential data/.
assumptions utilized, and the effects of the fire on nearby safe shutdown cables/
equipment. Show that this event at each pump location does not reduce the post fire shutdown capability of the plant below the requirements of Appendix R to 10 CFR Part 50.
8111040610 811026 PDR ADOCK 05000261 F
PDR OFFICE SURNAME DATE NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960
Mr. J A. Jones
-2 I hope this provides the information your staff desired.
Sincerely, Original signed by:
SA.Varg StevenA. VTarga, Chief Operating Reactors Branch #1 Division of Licensing cc:
See next page OR 1 ORB#
O FFICE)
SURNAME DATE
(/../81 0
81 NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960
Mr. J. A. Jones Carolina Power and Light Company cc: G. F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, D. C. 20036 Hartsville Memorial Library Home and Fifth Avenues Hartsville, South Carolina 29550 U. S. Nuclear Regulatory Commission Resident Inspector's Office H. B. Robinson Steam Electric Plant Route 5, Box 266-1A Hartsville, South Carolina 29550 Michael C. Farrar, Chairman Atomic Safety and Licensing Appeal Board Panel U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Richard S. Salzman Atomic Safety and Licensing Appeal Board Panel U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Dr. W. Reed Johnson Atomic Safety and Licensing Appeal Board Panel U. S. Nuclear Regulatory Commission Washington, D. C. 20555