ML19209C556
| ML19209C556 | |
| Person / Time | |
|---|---|
| Site: | Palisades, Turkey Point, Haddam Neck, Robinson, San Onofre, Yankee Rowe, Maine Yankee, Fort Calhoun |
| Issue date: | 09/04/1979 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Reid R, Schwencer A, Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910160136 | |
| Download: ML19209C556 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION I
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stp 4 1979 MEMCRANDUM FOR:
A. Schwencer, Chief, Operating Reactors Branch #1, 00R D. Ziemann, Chief, Operating Reactors Branch #2, D0R R. Reid, Chief, Operating Reactors 9 ranch #4, DOR FRCM:
G. Lainas, Chief, Plant Systems Brr.nch, 00R
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON STEAM GENERATOR WATER HAMMER The enclored request for additional infomation should be sent to certt.in licensees for Westinghouse and Combustion Engineering plants that are not equipped with top discharge devices on the steam generator feedwater spargers and for which there are no plans to modify the feedwater systems to reduce the probability of steam generator water hammer.
Those plants are listed in the enclosure.
Although a steam generator water hammer has not occurred in the present piping systems of those plants, we require some basis for further assurance that it will not occur in the future, that the capability exists for the detection of water haniner and that the NRC would be notified of such an event.
We have incorporated your cocinents of August 14, 1979 in the enclosed request for information.
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/G. Lainas, Chief Plant Systems Branch Divisien of Operating Reactors
Enclosure:
As stated
Contact:
S. 9.acKay X-27110 cc w/ enclosure:
See next page 1147 330 7 910180 / 3 b p
-2 SEP 4 1979 cc w/ enclosure:
D. Eisenhut B. Grimes S. Hanauer V. Benaroya G. Lainas E. Adensam E. Reeves S. MacKav Y. Huano D. Christiansen (EG&G J. Reece (Consultant)
W. Gammill R. Vollmer t
11A7 331
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ENCLOSURE 1 To FWR licensees for the following plants:
Haddam Neck Robinson 2 San Onofre 1 Turkey Point 3 and 4 Yankee Rowe Ft. Calhoun Maine. Yankee P;'.isades Gentlemen:
RE: STEAM GENERATOR WATER HAMMER In response to our letter of September 2,1977 regarding steam generator water hamer you indicated that, based on your operating experience, modifications were not necessary to further reduce the probability or consequences of steam generator water hamer 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 hamer will not occur in the future and that surveillance procedures would be adequate to detect water hamer or damage from water hammer if it were to occur.
Your response to the enclosed request for information, together with pre-vicusly supplied infomation, will provide a basis for a determination regarding the need for modifications to your feedwater system to prevent steam generator water hamer. Your response is needed within 60 days so that we may maintain our schedule for evaluating the potential for water hamer at your facility.
- Chief, Operating Reactors Branch d Division of Operating Reactors 1147 332
ENCLOSURE 1 REQUEST FOR INFORMATION REGARDING THE POTENTIAL FOR STEAM GENERATOR WATER HAMMER AT PRESSURIZED WATER REACTORS WITH FEEDRINGS THAT DISCHARGE FROM THE BOTTOM AUGUST 1979 e
1147 333
1.
Provide information that demonstrates that the feedwater system and steam generator water level at your facility have been subjected to those trans%nt conditions that are conducive to water hamer, i.e., the addition of cold feedwater 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 behavice 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 cf the plant. 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 feeowater for the purpose of reducing the probability of water hamer, show when they were adopted and give the ar.2wers to items 1.1,1.2 and 1.3 for before and af ter 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 hamer, show that an adequate water inventory and flow will be maintained to accomodate all postulated transient and accident conditions.
4.
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 hamer and possible damage from such an event.
Include all instrumentation that will be employed.
Describe the inspections that will be perfomed and give the frequency of such inspections.
6.
Describe the reporting procedures that will be used to document and report water hamer and damage to piping and piping support syste s.
Such repcrts were re:uested in our letter tc you dated Septe-ber 2, 1977.
P0000PLBINAL 1147 354
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