ML14184A110
| ML14184A110 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/18/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Jackie Jones Carolina Power & Light Co |
| References | |
| NUDOCS 7910090817 | |
| Download: ML14184A110 (5) | |
Text
Distrbutij SEPTEiBiR 18 1979 Di skt file 50-261 J. R. Buchanan NRC PDR TERA Local PDR ACRS NRR Rdg.
S. MacKay ORB Rdg.
Docket No. 50-261 D. Eisenhut B. Grimes Mr. J. A. Jones:
W. Gammill Senior Executive Vice President T. J. Carter Carolina Power and Light Company W Russell 336 Fayetteville Street Attorney, OELD Raleigh, North Carolina 27602.
OI&E (3)
A. Schwencer
Dear Mr.,
Jones:
D. Neighbors P. Kreutzer In response to our letter of September 2, 1977, regarding steam generator water hammer you indicated that, based on your operating experience; modi fications were not necessary to further reduce the probability or consequences of steam generator water hammer at your facility. Although-your operating history does not show that such water hammer has occurred in-your present piping arrangement, we require further assurance that steam generator water hammer will not occur, in the future and that surveillance procedures would be adequate to dettect water hammer or damage from water hammer if it were to occur.-,
Your response to the enclosed request for information, together with pre viously supplied information, will provide a'basis for a determination regarding the need for modifications to your feedwater system to prevent steam generator water hammer. Your response is needed within 60 days so that we may maintain our schedule for-evaluating the potential for water hammer at your facility.
Sincerely, Original Signed By A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors Enclosure cc: w/enclosure M
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 September 18, 1979 Docket No. 50-261 Mr. J. A. Jones:
Senior Executive Vice President Carolina Power and Light Company 336 Fayetteville Street Raleigh, North Carolina 27602
Dear Mr. Jones:
In response to our letter of September 2, 1977, regarding steam generator water hammer you indicated that, based on your operating experience, modi fications were not necessary to further reduce the probability or consequences of steam generator water hammer at your facility. Although your operating history does not show that such water hammer has occurred in your present piping arrangement, we require further assurance that steam generator water hammer will not occur in the future and that surveillance procedures would be adequate to detect water hammer or damage from water hammer if it were to occur.
Your response to the enclosed request for information, together with pre viously supplied information, will provide a basis for 3 determination regarding the need for modifications to your feedwater system to prevent steam generator water hammer. Your response is needed within 60 days so that we may maintain our schedule for evaluating the potential for water hammer at your facility.
Sincerely, A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors Enclosure cc: w/enclosure See next page
Mr. J. A. Jones Carolina Power and Light Company September 18, 1979 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
EN CLOSURE REQUEST FOR INFORMATION REGARDING THE POTENTIAL FOR STEAM GENERATOR WATER HAMMER AT PRESSURIZED WATER REACTORS WITH FEEDRINGS THAT DISCHARGE FROM THE BOTTOM SEPTEMBER 1979
Provide information tat demonstrates that the feeder system and steam generator water level at your facility have been subjected to those transient conditions that are conducive to water hamer, i.e., the addition of cold feLdwater or auxiliary feedwater to steam-filled feedwater piping and feedring. See NUREG 0291 Page 4 that was forwarded to you on September 2, 1977.
Include the following:
1.1 Describe the expected behavior of steam generator water level as a result of reactor trip from power levels greater than 30% of full power. Include actual plant measurements of steam generator level and other available related data such as feedwater flow and auxiliary feedwater flow.
1.2 Provide the number and causes of loss of feedwater events during the operational history of the plart. You may refer to material submitted previously.
1.3 Provide the number and causes of loss of off-site power events during the operational history of the plant.
2..
If administrative controls have been adopted to limit the flow of auxiliary -feedwater for the purpose of reducing the probability of water harrner, show when they were adopted and give the answers
- to items 1.1, 1.2 and 1.3 for before and after such controls were established.
- 3. If administrative controls have been adopted to limit the flow of auxiliary feedwater for the purpose of reducing the probability of water hammer, show that an adequate water inventory and flow will be maintained to accomodate all postulated transient and accident conditions.
If auxiliary feedwater flow in your facility is not at present initiated automatically for normal and accident events, present your evaluation of whether automating the actuation of auxiliary feedwater might increase the probability of inducing steam generator water hammer.
One of the signals that would automatically initiate the flow of auxiliary feedwater would be the.steam generator low water level.
This set point should be above the top of the main feedwater sparger to reduce the probability of steam generator water hammer.
- 5. Describe the means that will be used to monitor for the occurrence of steam generator water hammer and possible damage from such an event.
Include all instrumentation that will be em.ployed.
Describe the inspections that will be performed and give the frequency of such inspections.
escribe the reporting procedures that will be used to document and report water hammer and damage to piping and pIping support s 7e.
Such reports were recuested in our letter to you dated SepteMber 2, 1977.