ML17250A818
| ML17250A818 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/20/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | White L ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| LSO5-80-11-028, LSO5-80-11-28, NUDOCS 8012190329 | |
| Download: ML17250A818 (18) | |
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Cw Nr. Leon D. White, Jr.
Vice President Electric and Steam Production 89 East Avenue Rochester, New York 14649
Dear Hr. White:
SUMECT:
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 underwear.
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.
OFFICE/
SURNAME DATEP NRC FORM 318 (9 76) NRCM 0240 AU.S. GOVERNMENT PRINTING OFFICE: 1979 289 369
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Mr. Leon D. White, Jr.
In order for the information from operating plants to be used as input to this series of sump test, which will 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,
Enclosure:
As, stated cc: w/enclosure See next page Dennis M. Crutchfield, Chief Operating Reactors Branch 85 Division of Licensing DISTRIBUTION:
Docket NRC PDR Local PDR TERA NSIC NRR Reading ORB t5 Reading DEisenhut RPurple TNovak RTedesco GLainas JRoe JHeltemes DCrutchfield HSmith RSnaider OELD OISE (3)
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 November 20, 1980 Docket No. 50-244 LS05-80-11-028 Mr. Leon D. White, Jr.
Vice President Electric and Steam Production 89 East Avenue Rochester, New York 14649
Dear Mr. White:
SUMECT:
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.
I'
Mr. Leon D. White, Jr.
November 20, 1980 In order for the information from operating plants to be used as input to this series of sump test, which will coranence 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,
Enclosure:
As stated Dennis M. Crutchfield, C
ef Operating Reactors Branch 85 Division of Licensing cc: w/enclosure See next page
ea ll ~
P
Mr. Leon D. White, Jr.
3 November 20, 1980 cc w/enclosure:
Harry H. Voigt, Esquire LeBoeuf, Lamb, Leiby and MacRae 1333 New Has@shire
- Avenue, N. M.
Suite 1100 Mashington, D. C.
20036 Mr. Michael Slade 12 Trai lwood Circle Rochester, New York 14618 Rochester Comnittee for Scientific Information Robert E. Lee, Ph.D.
P. 0.
Box 5236 River Caapus Station Rochester, New York 14627 Jeffrey Cohen New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontari o 107 Ridge Road West
- Ontario, New York 14519 Resident Inspector R. E. Ginna Plant c/o U. S.
NRC 1503 Lake Road
~
- Ontario, New York 14519 Ezra I. Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 Morld Trade Center New York, New York 10047 Director, Criterid and Standards Division Office of Radiation Programs (ANR-460)
U. S. Environmental Protection Agency Mashington, D. C.
20460 U. S. Environmental Protection Agency Region II Office ATTN:
EIS COORDINATOR 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,
Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Coamission Mashington, D. C.
20555 Dr.
Richard F. Col e Atomic S afety and Licens ing Board U. S. Nuclear Regulatory Comnission Washington, D. C.
20555 Dr. Eameth A. Luebke Atomic Sa fety and Licens ing Board U. S. Nuclear Regulatory Coomission Washington, D. C.
20555 Mr. Thomas B. Cochran Natural Resources Defense Council, Inc.
1725 I Street, N.
W.
Suite 600 Washington, D. C.
20006
4 H'
Information Re uest From 0 eratin 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 fulfillthis request.
2.
For each type of'hermal insulation used in the containment (particularly within the crane wall envelope),
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.
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 November 20, 1980 Docket No. 50-244 LS05-80-11-028 Mr. Leon D. Mhite, Jr.
Vice President Electric and Steam Production 89 East Avenue Rochester, New York 14649
Dear Mr. Mhite:
SUBJECT'NfORMATION 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) i nadequate 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) i nadequate 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 undemay.
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.
>C
Mr. Leon D. White, Jr. November 20, 1980 In order for the information from operating plants to be used as input to this series of sump test, which will 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.
S incerely,
Enclosure:
As stated Dennis M. Crutchfield, C 'ef Operating Reactors Branch g5 Division of Licensing cc: w/enclosure See next page
J A
I
Nr. Leon D. White, Jr.
3 November 20, 1980 cc w/enclosure:
Harry H. Voigt, Esquire LeBoeuf, Lamb, Leiby and NacRae 1333 New Hampshire Avenue, N. M.
Suite 1100 Mashington, D. C.
20036 Mr. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Rochester Coranittee for Sci ent ific Informati on Robert E. Lee, Ph.D.
P. 0.
Box 5236 River Campus Station Rochester, New York 14627 Jeffrey Cohen New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza
- Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontario 107 Ridge Road Mest
- Ontario, New York 14519 Resident Inspector R. E. Ginna Plant c/o U ~
S NRC 1503 Lake Road
- Ontario, New York 14519 Ezra I. Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Director, Criteria and Standards Division Office 'of Radiation Programs (ANR-460)
U. S. Envir'onmental Protection Agency Washington, D. C.
20460 U. S. Environmental Protection Agency Region II Office ATTN:
E IS COORD INATOR 26 Federal Plaza
'ew York, New York 10007 Herbert Grossman, Esq.,
Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Mashington, D. C.
20555 Dr. Richard F. Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C.
20555 Dr. Emneth A. Luebke Atomic Saf ety and Licens i ng Board U. S. Nuclear Regulatory Comnission Washington, D. C.
20555 Mr. Thomas B. Cochran Natural Resources Defense Council, Inc.
1725 I Street, N.
W.
Suite 600 Mashington, D. C.
20006
~
~
Information Re uest From 0 eratin PMR 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 fulfillthis request.
2.
For each type of thermal insulation used in the containment (particularly within the crane wall envelope),
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 i n containment of each type.