ML17209A361
| ML17209A361 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 11/07/1980 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| References | |
| NUDOCS 8011210050 | |
| Download: ML17209A361 (7) | |
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'f'y, Docket No. 50-335 DISTRIBUTION:
Docket file JHeltemes gQ'4I'y ]gap NRC PDR L POR G. ~~
TERA NSIC ORB83 Rdg NRR Rdg DEisenhut RPurple TNovak RTedesco Dr. Robert E. Uhrig GLainas
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Vice President JRoe
'dvanced Systems 5 Technology OELD Florida Power 8 Light Company OIQE (3)
P. 0.
Box 529100 RAClark Miami, Florida 33152 CNelson PWagner (a)
Dear Dr. Uhrig:
PNKreutzer (3)
ACRS (16).
SUBJECT:
INFORMATION REqUEST REGARDI3gef@hT44NtlENT SUNPS AND INSULATION FOR OPERATING REACTORS, TAP A-43 8
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CO (Xl C3 During our reviews of license applications we have identified concerns related to the containment sump design and its effect on long term cooling following a Loss of Coolant Accident (LOCA).
These concerns are related to:
(1) creation of debris which would potentially block the sump screens and flow passages in the ECCS and the core, (2) inadequate NPSH of the pumps taking suction from the containment
- sump, (3) air entrainment from streams of water or steam which can cause loss of adequate NPSH, (4) formation of vortices which can cause loss of adequate NPSH, air entrainment and suction of floating debris into the ECCS and (5) inadequate emergency procedures and operator training to enable a correct response to these problems.
Preoperational recirculation tests performed by utilities have consistently identified the need for plant modifications.
The NRC has, therefore, begun a generic program to resolve these concerns-As part of the Unresolved Safety Issue (USI) effort to evaluate the performance of containment sumps for operating reactors (TAP A-43, Containment Emergency Sump R.eliability), a series of sump tests covering typical designs will be performed under contract by the Alden Research Laboratory.
The test facility has been constructed and shakedown testing is undeniay.
Information from operating reactor licensees is required to assist us in developing the appr opriate range of test parameters and to evaluate the potential significance of debris formation from insulation materials'within containment.
OFFICE P i SURNAME DATEP.
NRC FORM 318 (9-76) NRCM 0240 QS0 AU.S. GOVERNMENT PRINTING OFFICE: 1979.289-369
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In order for the information from operating plants to be used as input to this series of sump test, vkich commenced.:in..0dtobet:='"r
- 1980, we request that you provide the data requested in the enclosure to this letter within 90 days of its receipt. If you have any questions on this subject, please contact us.
Since ely,
Enclosure:
As stated cc: w/enclosure Service List br>g)nW stgney by:
Robert A. Clark, Chief Operating Reactors Branch b3 Division of Ljcensing ORB 3:
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SURNAME DATEP NRC FORM 318 (9.76/ NRCM 0240 ORBg3:DL C
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Florida Power 5 Light Company CC:
Robert Lowenstein, Esquire Lowenstein,
- Newman, Reis 5 Axelrad 1025 Connecticut
- Avenue, N.M.
l'ashington, D.C.
20036 Norman A. Coll, Esquire YicCarthy, Steel, Hector E Davis 14th Floor, First Nati'onal Bank Building Hiami, Florida 33131 Indian Piver Junior College Library 320 Vl rgiMa Av nue Fort Pierce, Florida 33450
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Envi ronmenta 1
Regul a t i on Power Pier'. Siting Section Sta =e o
Florida 260
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Lewis County Ao.-..;ni strator St.
Luc>e Coun:y 2300 Yiroinia Avenue, Room 104 Fort Pierce, Florida 33450 Hr. Jack Shreve Office of the Public Counsel Room 4, Holland Bldg.
Tallahassee, Flor da 32304 Bureau of Intergovernmental Relations 660 Apalachee Parkway Ta',lahassee, Florida
.- 32304 Resident Inspector/St.
Lucie Nuclear Power Station c/o U.S.N.R.C P.O.
Box 400 Jense!'.
Bcacn, Florida 33457
- Director, T chnical Division Of;ice of Radiation (u;:-45":)
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Informati'on Re vest From Ooeratina PHR Licensees 1.
Provide a drawing o
the containment sump showing important design features (e.g.,
debris screening, divider plates, etc.)
and dimensions.
Provide a drawing showing location in the containment building and th' location relative to the reactor primary system.
The location and configura;ion of the suction 1 ines for recirculation, relative to the containment sump should also be shown.
For acilities which have performed success ul sump flov; tests, reference to the docketed results= of those tes-.s will fulfillthis request.
2.
For each type of thermal insulation used in.he containment (particularly within the crane wall envelop), provide tne following irformation:
a) type of material including composi:ion and density; b) manufacturer and brand name; c) method of attachment; d) location and quant'ty in conta'inment of each type.
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