ML20136C616

Summary of 790822 Meeting W/Util in Bethesda,Md Re Containment Ventilation Sys Dampers (Ventilation Sys Isolation Valves) Reliability.List of Attendees Encl

ML20136C616
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	09/11/1979
From:	James Shea Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TASK-06-04, TASK-6-4, TASK-RR NUDOCS 7909290289
Download: ML20136C616 (5)

Text

( l l SEP 111979 1

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Docket No. 50-409 d$$IMOh.;h,_ hdy] g '

LICENSEE: Dairyland Power Cooperative (DPC)

FACILITY: Lacrosse Boiling Water Reactor (LACBWR)

SUBJECT:

SURtARY OF MEETING HELD ON AUGUST 22, 1979 I

NRC and DPC representatives met in Bethesda, Maryland, on August 22, 1979, to review containment ventilation system dampers (ventilation system isolation valves) reliability. The meeting attendees are listed in the attachment.

By letter dated February 1,1979, DPC responded to NRC letter dated November 29, 1978, titled " Containment Purging During Normal Plant Operation." The NRC sited two specific events that had occurred recently that raised several questions relative to potential failures of automatic isolation of the large diameter (up to 48 inches in diameter) purge penetrations which are used during power operation. In both of these events, the isolation signals required to automatically close the purge valves for containment integrity were manually overridden to allow containment purging with radiation levels above the signal normally

required automatic valve closure. Our November 29, 1978 letter requested that utilities of operating plants provide a commitment to cease contain-ment purging during reactor operation or justify continued purging. DPC noted in its letter of February 1,1979, that the LACBWR containment building was originally designed for continuous ventilation. This feature was reviewed and found acceptable by NRC when the LACBWR was initially authorized for power operation.

The LACBWR containment building ventilation system has five 20-inch flanged butterfly valve-type dampers. The dampers are located inside the containment vessel. Four of the dampers would be used in the event of an accident involving release of radioactivity to the containment atmosphere to seal the containment ventilation system to prevent a potentially excessive release of radioactive fission products to the atmosphere. Two of the four dampers are in series in the inlet duct (redundant valves) and two are in the exhaust duct (redundant). The fifth damper is located in the recirculation duct and is normally closed but is designed to open when the four isolation valves close to pennit internal recirculation if the structure is not pressurized or heated excessively.

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- Dairyland Power Cooperative SEP 111979 CC ,

• Fritz Schubert, Esquire Staff Attorney ,

Dairyland Power Cooperative 2615 East Avenue South La Crosse, Wisconsin 54601 O' S. Heistand, Jr., Esquire Morgan, Lewis & Bockius .

1800 M Street, N. W.

Washington, D. C. 20036 Mr. R. E. Shimshak La Crosse Boiling Water Reactor Dairyland Power Cooperative P. O. Box 135 Genoa, Wisconsin 54632 Coulee Region Energy Coalition ATTN': George R. Nygaard P. O. Box 1583 La Crosse, Wisconsin 54601 Charles Bechhoefer, Esq., Chairman

. - Atomic Safety and Licensing Board U. S. Nuclear Regulatory Cornission Washington, D. C.~ 20555 Dr. George C. Anderson Department of Oceanography University of Washington Seattle, Washington 98195 Mr. Ralph S. Decker Route 4, Box 1900 Cambridge, Maryland 21613 La Crosse Public Library 800 Main Street La Crosse, Wisconsin 54601

. Mr. Frank Linder General Manager Dairyland Power Cooperative 2615 East Avenue South La Crosse, Wisconsin 54601 l

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Dairyland Power Cooperative I

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DPC presented additional information (and later agreed to document the details of the oral presentation) that supplemented their February 1979 submittal. The DPC presentation covered the items listed below:

1. Basic Valve Design (Exhibits).

2. Application and Operating Parameters and Response.

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3. Test flistory - Maintenance Experience.

, 4. Radiological Impact of Non-Ventilation.

i l 5. Operational Impact of Non-Ventilation-Surveillance, Exposure.

, 6. Sensible Heat Rise with Hon-Ventilation.

l l 7. Reliability Conversations with Manufacturer.

l 8. Optional Test Program.

9. LOCA Qualifications Sensing and Operation Circuitry.

! 10. LOCA Qualifications for Valve.

l The containment ventilation damper valves were designed originally to

, close on:

1. high radioactivity in the containment exhaust duct.

2. high reactor pressure.

3. high containment pressure.

4. loss of electrical power supply.

5. nanual operation from control room.

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l Dairyland Power Cooperative SEP 111979 i

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! DPC is currently negotiating to perfonn vent valve closure tests to l demonstrate valve closure reliability. It is tentatively planned that the tests would be perfonned at Langley Field, Virginia, after reaching accord with the valve manufacturer, Allis Chalmers, and NRC. The NRC re-evaluation of containment ventilation dampers closure reliability to further enhance the health and safety of the public will continue when the additional infonnation to be provided by DPC and the valve qualiff-

cation test results are available for review. <

~

~ James J. Shea, Project Manager

, Operating Reactors Branch #2 Division of Operating Reactors

Attachment:

List of Attendees cc:

See next page i

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i MEETING

SUMMARY

. DISTRIBUTION:

T Docket 50-409 ;

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! Local"PDR

, .f0RBf2 Reading 2'

NRR Reading

,' , 11. R. Denton i

E. G. Case

[- D. Eisenhut i R. Vollmer B. Grimes l W. Ganmill '

j J. Miller L. Shao T. Carter D. Crutchfield D. Ziemann '

V. Noonan Seismic Review Group A. Schwencer T. Ippolito R. Reid G. Lainas P. Check R. Clark F. Pagano G. Knighton J. Shea

11. Smith OELD OI&E(3)

R. Fraley, ACRS(16)

L. Nichols E. Reeves J. Shapaker T. Quay J. Kerrigan S. Brown J. Wetmore P. Tam (ACRS)

J. R. Buchanan TERA JOSn 's' Y va l

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i ATTACHMENT i

LIST OF ATTENDEES

,, .,: AUGUST 22, 1979

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l DPC' H. A. Towsley i

L. J. Krajewski

B. Angle l i R. Shimshak

.4 NES Inc.

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R. Milos

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R. O. Smith i

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i J. Shea L. Nichols

! E. A. Reeves J. W. Shapaker T. Quay J. Kerrigan S. Brown

J. Wetmore P. Tam (ACRS) i 1

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