ML19343A610
| ML19343A610 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 09/22/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Linder F DAIRYLAND POWER COOPERATIVE |
| References | |
| REF-GTECI-B-24, REF-GTECI-ES, TASK-B-24, TASK-OR NUDOCS 8011190129 | |
| Download: ML19343A610 (4) | |
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UNITED STATES
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September 22, 1980 P
8 Docket No. 50-409 5'!
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Mr. Frank Linder
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Dear Mr. Linder:
RE:
Task No. B-24 i
We are continuing our review of bypass and reset of engineered safety features at the La Crosse Boiling Water Reactor and have found that addi-tional information described in the enclosure to this letter is needed.
We request your response within 45 days of your receipt of this letter.
Si cerely, 2.dubtd OperatingRe6ctorsBran[ch#5 ennis M. Cr:tevield, ief Division of Licens ng
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page e
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Mr. Frank Linder September 22, 1980 cc Fritz Schubert, Esquire Director, Technical Assessment Staff Attorney Division Dairyland Power Cooperative Office of Radiation Programs 2615 East Avenue South (AW-459)
La Crosse, Wisconsin 54601 U. S. Environmental Protection Agency O. S. Heistand, Jr., Esquire Crystal Mall #2 Morgan, Lewis & Bockius Arlington, Virginia 20460 1800 M Street, N. W.
Washington, D. C.
20036 U. S. Environmental Protection Agency Mr. R. E. Shimshak Federal Activities Branch La Crosse Boiling Water Reactor Region V Office Dairyland Power Cooperative ATTN: EIS C0ORDINATOR P. O. Box 135 230 South Dearborn Street Genoa, Wisconsin 54632 Chicago, Illinois 60604 Coulee Region Energy Coalition Charles Bechhoefer, Esq., Chairman ATTN: George R. Nygaard Atomic Safety and Licensing Board P. O. Box 1583 U. S. Nuclear Regulatory Comission La Crosse, Wisconsin 54601 Washington, D. C.
20555 La Crosse Public Library Dr. George C. Anderson 800 Main Street Department of Oceanography La Crosse, Wisconsin 54601 University of Washington Seattle, Washington 98195 Mrs. Ellen Sabelko Society Against Nuclear Energy Mr. Ralph S. Decker 929 Cameron Trail Route 4 Box 190D Eau Claire, Wisconsin 54701 Cambridge, Maryland 21613 Town Chairman Dr. Lawrence R. Quarles Town of Genoa Kendal at Longwood, Apt. 51 Route 1 Kenneth Square, Pennsylvania 19348 Genoa, Wisconsin 54632 Thomas S. Moore Chairman, Public Service Comission Atomic Safety and Licensing Appeal Board of Wisconsin U. S. Nuclear Regulatory Comission Hill Farms State Office Building Washington, D. C.
20555 Madison, Wisconsin 53702
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Ms. Anne K. Morse Alan S. Rosenthal, Esq., Chairman Coulee Region Energy Coalition Atomic Safety and Licensing Appeal Board Post Office Box 1583 U. S. Nuclear Regulatory Comission Lacrosse, Wisconsin 54601 Washingtun, D. C.
20555 U. S. Nuclear Regulatory Comission Mr. Frederick Milton Olsen, III Resident Inspectors Office 609 North lith Street Rural Route #1, Box 225 Lacrosse, Wisconsin Genoa, Wisconsin 54632
s LACROSSE c
REQUEST FOR ADDITIONAL INFORMATION BYPASS AND RESET OF ENGINEERED SAFETY FEATURES 1.
The infonnation presented in your SAR and your letters of February 1, 1979 and January 14, 1980, is not sufficient to determine if the following requirements are met for the safety signals to all Engineered Safety Features (ESF) equipment.
Therefore, identify and justify all exceptions to the following:
Criterion 1 - in keeping with the requirements of General Design Criteria 55 and 56, the overridinga of one type of safety actuation signal, e.g., radiation, should not cause the blocking of any other type of safety actuation signal, e.g., pressure, for those valves that have no function besides containment isolation.
Criterion 2 - Sufficient physicci features e.g., key lock switches, are to be provided to facilitate adequate administrative controls.
Criterion 3 - A system level annunciatien of the overridden status should be provided for every safety system impacted when any override is active.
(See R.G. 1.47.)
Criterion 4 - Diverse signals should be provided to initiate isolation of the containment ventilation system.
Specifi; ally, containment high radiation, safety injection actuation, and containment higi, pressure (where containment high pressure is not a portion of safety injection actuation) should automatically initiate containment ventilation isolation.
Criterion 5 - The instrumentation and control systems provided to initiate the ESF should be designed and qualified as safety grade equipment.,
b Criterion 6 - The overriding or resetting of the ESF actuation signal should not cause any valve or damper to change position.
ine following oefinitions are given for clarity of use:
a - Override:
the signal is still present, and it is blocked in order to perform a function contrary to the signal.
The term " override" where used in this Request for Infomation, includes functionally equivalent techniques of signal modification, e.g., " bypass."
b - Reset-the signal has come and gone, and the circuit is ben g cleared in order to return it to normal condition, f
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2.
The NRC requires that all override and reset switches have physical provisions to aid in the administrative control of the override or reset function.
Discuss the physical provisions supplied with your manual radiation channel pushbutton reset switches and the manual auxiliary relay pushbutton reset switches (ROGH, R0GG, VDX1 and VDX).
If no such provisions are presently provided, how do you intend to comply with this requirement?
3.
The NRC requires that, as a minimum, containment ventilation isolation be accomplished on any of the following:
a.
Containment pressure high b.
Safety injection c.
Containment radiation high.
Your 20-inch isolation dampers do not isolate on safety injection.
(Your 4-inch vent header valves do r<ot isolate on safety injection or on high radiation.) How do you intend to meet this requirement?
4.
The NRC requires signals that initiate containment isolation be derived from safety-grade (class lE) equipment.
Discuss the qualifications of the equipment used presently and the equipment that is needed to meet requirement 3 above.
If any is not of safety-grade, how do you intend to upgrade them to safety-grade?
5.
Reference (b) indicates that both redundant 20-inch dampers are located inside containment (for both inlet and exhaust).
General Design Criteria (GDC) 56 does not permit this.
Discuss the acceptability of the design on some othec defined basis.
6.
Reference (c) indicates that CS contacts to both strings of valve control are common to the same switch in the control room.
Discuss how this design complies with GDC 21 ("no single failure results in the loss of a protection function").
References (a) NRC generic letter to all Power Reactor Licensees, " Containment Purging During Normal Plant Operation," November 28, 1978.
(b)
DPC letter, F. Linder, to Director of Nuclear Reactor Regulation, U.S.N.R.C., " Containment Purging During Norr.al Plant Operation,"
February 1, 1979, LAC-6104.
(c) DPC letter, F. Linder, to Director of Nuclear Reactor Regulation, U.S.N.R.C., "IE Bulletin No. 79-08, Additional Information, Events Relating to BWRs Identified During Three Mile Island Incident,"
January 14, 1980, LAC-6732.
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