ML20002B204

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Forwards Request for Info Re Containment Sumps & Insulation. Info from Operating Reactors Is Needed to Develop Range of Test Parameters & Evaluate Significance of Debris Formation
ML20002B204
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 11/18/1980
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Counsil W
CONNECTICUT YANKEE ATOMIC POWER CO.
References
LS5-80-11-23, LSO5-80-11-023, LSO5-80-11-23, NUDOCS 8012110076
Download: ML20002B204 (4)


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November 18, 1980 Docket No. 50-213 LS05-80-11-023 3

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N Mr. W. G. Counsil, Vice President

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Dear Mr. Counsil:

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 tem cooling folicwing 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 perf ormance 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.

80121100 No g.

' Mr. W. G. Counsil November 18, 1980 In order for the.infomation from operating plants to be used as input to this series of sump tests, which will commence in October 1980, we request that you provide the data requested in tne enclosure to this letter within 90 days of its receipt.

If you have any questions on this subject, please contact us.

Sincerely, k.

Dennis M. Crutchfield, ief Operating Reactors Bra ch #5 Division of Licensing As stated cc: w/ enclosure See next page

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Mr. W. G. Counsil November 18, 1980 cc w/ enclosure:

Day, Berry & Howard U. S. Environmental Protection Counselors at Law Agency One Constitution Plaza Region 1 Office Hartford, Connecticut 06103 ATTN: EIS COORDINATOR JFK Federal Building Superintendent Boston, Massachusetts 02203 Maddam Neck Plant RFD #1 Resident Inspector Post Office Box 127E Haddam Neck Nuclear Power Station East Hampton, Connecticut 0642, c/o U. S. NRC East Haddam Post Office Mr. James R. Himmelwright East Haddam, Connecticut 06423 Northeast Utilities Service Conpany P. O. Box 270 Hartford, Connecticut 06101 Russell Library 119 Broad Street Middletown, Connecticut 06457 Board of Selectmen Town Hall Haddam, Connecticut 06103 Connecticut Energy Agency ATTN: Assistant Director Research and Poli;y Development Department of Planning and Energy Poliqr 20 Grand Street Hartford, Connecticut 06106 Director, Criteria and Standards Division Office of Radiation Prograns (ANR-460)

U. S. Environmental. Protection Agency Washington, D. C.

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Information Request From 06erating PWR Licensees L

1.

Provide a drawing of the containment sump show ng important design

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i 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 envelope), provide the following information:

A 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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