ML14192A092
| ML14192A092 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/31/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Jackie Jones Carolina Power & Light Co |
| References | |
| REF-GTECI-A-43, REF-GTECI-EN, TASK-A-43, TASK-OR NUDOCS 8011170651 | |
| Download: ML14192A092 (6) | |
Text
~ 3 11980 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:
SUBJECT:
INFORMATION REQUEST REGARDING CONTAINMENT SUMPS AND INSULATION FOR OPERATING REACTORS, TAP A-43 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 Reliability), 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 underway. Information from operating reactor licensees is required to-assist us in developing the appropriate range of test parameters and
-to evaluate the potential significance of debris formation from insulation materials within containment.
so11ob5 O FFIC E SU RNA M E D A T E NRC FORM 318 (9-76) NRCM 0240
- U.S.
GOVERNMENT PRINTING OFFICE: 1979-289-369
Mr. J. A. Jones Carolina Power. and Light Company 2
In order for the information from operating plants to be used as input to this series of sump tests, which were to commence in October 1980, wIe 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.
Sincerely, Original digned byr S. A. Vc:rga Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing
Enclosure:
As Stated cc:
w/enclosure See next page Distribution Docket File 50-261 NRC PDR Local PDR TERA NSIC NRR Reading ORB1 Reading T. Novak S. Varga
- 0. Neighbors P. Wagner C. Parrish J. Roe J. Heltemes I&E (3)
Attorney, OELD SOFFICE BDL
- ORB1 p
,URNAME 9.o j SAVarga _
9 DATE t..
O NRC FORM 318 (9-76) NRCM 0240
- U.S.
GOVERNMENT PRINTING OFFICE: 1979-289-369
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 October 31, 1980 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:
SUBJECT:
INFORMATION REQUEST REGARDING CONTAINMENT SUMPS AND INSULATION FOR OPERATING REACTORS, TAP A-43 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 Reliability), 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 underway. Information from operating reactor licensees is required to assist us in developing the appropriate range of test parameters and to evaluate the potential significance of debris formation from insulation materials within containment.
Mr. J. A. Jones Carolina Power and Light Company October 31, 1980 In order for the information from operating plants to be used as input to this series of sump tests, which were to commence in October 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.
Sincerely, te v en A.( at a, h'
Operating Reactors anch #1 Division of Licensing
Enclosure:
As Stated cc: w/enclosure See next page
Mr. J. A. Jones Carolina Power and Light Company October 31, 1980 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 Michael C. Farrar, Chairman Atomic Safety and Licensing Appeal Board Panel U. S. Nuclear Regulatory Commission Washington, 0. 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
Information Request From Operatina PWR Licensees
- 1. Provide a drawing of 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 the location relative to the reactor primary system. The location and configuration of the suction lines for recirculation, relative to the containment sump should also be shown. For facilities which have performed successful sump flow tests, reference to the docketed results of those tests will fulfill this request.
- 2. For each type of thermal insulation used in the containment (particularly within the crane wall envelop), provide the following information:
a) type of material including composition and density; b) manufacturer and brand name; c) method of attachment; d) location and quantity in containment of each type.