ML20039E850
| ML20039E850 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 01/05/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Linder F DAIRYLAND POWER COOPERATIVE |
| References | |
| REF-GTECI-B-24, REF-GTECI-EL, REF-GTECI-ES, TASK-06-04, TASK-6-4, TASK-B-24, TASK-OR, TASK-RR LSO5-82-01-005, LSO5-82-1-5, NUDOCS 8201110545 | |
| Download: ML20039E850 (10) | |
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TD Januarv 5.1982 Docket No. 50-409 M h' LS05 01-005
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Dairyland Power Cooperative
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Lacrosse, Wisconsin 54601 X.
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Dear Mr. Linder:
SUBJECT:
SEP TOPIC VI-4, 0VERRIDE OF CONTAINMENT PURGE ISOLATION AND OTHER ESF ACTUATION SIGNALS (LACROSSE)
The staff has determined that the scope of review and evaluation perfonned for multi-plant generic activity B-24 includes the electrical aspects of SEP Topic VI-4.
Additional review and evaluation is, therefore, not required.
Enclosed is a copy of our revised evaluation of the electrical portion of generic activity B-24 for Lacrosse.
This assessment conpares your facility, as described in Docket No. 50-409, with the criteria currently used by the regulatory staff for lice-tsing new facilities. The report has been modified to reflect the comments contained in your August 26, 1981, letter.
This safety evaluation is the staff's position regarding design of your facility in the subject area. With regard to the referenced topic, the staff has concluded your facility meets current licensing criteria.
Sincerely, 50' 6
Jj lil gu a4E (3b Dennis M, Crutchfield, Chief Operating Reactors Branch No. 5 AoD' Division of Licensing 4
Enclosure:
As stated cc w/encicsure:
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v>w NRC FORM 318 DO-80) NHCM ONO OFFICIAL RECORD COPY usom mi-ass-eea
p Mr.~ Frank Linder AJ' cc Fritz Schubert Esquire U. S. Environmental Protection ~
Staff Attorney Agency Dairyland Power Cooperative Federal Activities Branch 2615 East Avenue South Region V Office La Crosse, Wisconsin 54601 ATTN: Regional Radiation Representative 230 South Dearborn Street-O. S. Heistand, Jr., Esquire Chicago, Illinois 60604 Morgan, Lewis & Bockius 1800 M Street, N. W.
Mr. John H. Buck 1
Washington, D. C.
20036 Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Mr. R. E. Shimshak Washington, D. C.
20555 La Crosse Boiling Water Reactor Dairyland Power Cooperative Dr. Lawrence R. Quarles P. O. Box 135
.Kendal at Longwood, Apt. 51 Genoa, Wisconsin 54632 Kenneth Square, Pennsylvania 19348 Ms. Anne K. Morse Charles Bechhoefer, Esq., Chairman Coulee Region Energy Coalition Atomic Safety and Licensing Board P. O. Box 1583 U. S. Nuclear Regulatory Commission 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 U. S. Nuclear Regulatory Commission Resident Inspectors Office Mr. Ralph S. Decker Rural Route #1, Box 276 Route 4, Box 190D Genoa, Wisconsin 54632 Cambridge, Maryland 21613 Town Chairman Thomas S. Moore Town of Genoa Atomic Safety and Licensing Appeal Board Route 1 U. S. Nuclear Regulatory Commission Genoa, Wisconsin 54632 Washington, D. C.
20555 Chairman, Public Service Commission Mr. George R. Nygaard of Wisconsin Coulee Region Energy Coalition Hill Farms State Office Building 2307 E.ast Avenueu Madison, Wisconsin. 537.02 Lacrosse, Wiscons-in 54601,
Alan S. Rosenthal, Esq., Chairman Atomic Safety and Licensing Appet' Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555
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Mr. Frederick Milton 01sen, III 609 North lith Street Lacrosse, Wisconsin 54601 a
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't SAFETY EVALUATION REPORT
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LACROSSE OVERRIDE OF CONTAINMENT PURGE ISOLATION'AND OTHER ENGINEERED SAFETY FEATURE ACTUATION' SIGNALS INTRODUCTION Instances have been reported at nuclear power plants where the intended automatic closure of the containment purge / ventilation valves during a postulated accident would not have occurred because the safety actuation signals were inadvertently overriden and/or blocked, due to design deficiencies.
These instar.ces were determined to constitute an Abnormal Occurrence (#78-5). As a follow-up action, L
NRR issued a generic letter reauesting each licensee to take certain actions.
EVALUATION The enclosed report " Electrical, Instrumentation, and Control Aspects of the Overriden of Containment Purge Valve Isolation" (EGG-EA-5564) was prepared for i
us by.EG&G, Idaho, as part of our technical assistance contract progrant The report provides their technical evaluation of the design compliance with 'NRC-provided criteria.
It identifies one area where the ventilation valves do not satisfy our criteria.
The area of concern is that the containment is not isolated automatically when the core spray system is initiated manually.
However, the plant does not have a system level manual initiation of core spray, therefore the present design is acceptable.
.The question raised by the contractor regarding GDC-56 will be covered by the mechanical system review being performed under SEP Topic VI-4.
I CONCLUSION 1
The staff finds the present design for the electrical overrides and bypasses to i
be acceptable.
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Tonu tas ;3ee e.,nn, INTERIM REPORT 3.[
Accession No.
Report No.
EGG-EA-5564 Contract Program or Project
Title:
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Electrical, Instrumentation, and Control Systems Support for the 7
Systematic Evaluation Program (II)
Subject of this Document Systematic Evalbation Program Topic VI-4, Electrical, Instrumentation and Control Aspects of the Override of Containment Purge Valve Isolation, La Crosse Boiling Water Reactor Type of Document:
Informal Report Author (s):
A. C. Udy D:.te of Document:
September 1981 R:sponsible NRC Individual and NRC Office or Division:
Ray F. Scholl, Jr., Division of Licensing This document was prepared primarily for preliminary orinternal use. it has not received full review and approval. Since there may be substantive chan,ges. this document should not be considered final.
EG&G Idaho, Inc.
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Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C.
Under DOE Contract No. DE-AC07 76 f D01579 NRC FIN No.
A6425 INTERIM REPORT
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SYSTEMATIC EVALUATION PROGRAMS q...
TOPIC VI-4 ELECTRICAL, INSTRUMENTATION, AND CONTROL ASPECTS OF THE OVERRIDE OF CONTAINMENT PURGE VALVE ISOLATION LA CROSSE BOILING WATER REACTOR 6
Docket No. 50-409
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September 1981
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A. C. Udy Reliability and Statistics Branch Engineering Analysis Division EG&G Idaho, Inc.
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CONTENTS 1.0 I NTR O D U C T I O N.................. c.................................
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2.0 EVALUATION OF THE LA CROSSE'B0ILING WATER REACTOR 5-o -
2 2.1 Review Guidelines.........................................
2 2.2 Containment Ventilation Isolation Circuits Design D e s c r i p t i c '1...............................................
~3 2.3 Containment Ventilation Isolation System Design
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Evaluation 4
2.4 Other Related Engineered Safety Feature System Circuits 5
3.0 SUNHARY 5
4.0 REFERENCES
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SYSTNTIC. EVALUAT[Si?. PROGRAM l
TOPIC VI-4 gi
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ELECTRICAL,. INSTRUMENTATION,.AND CONTROL. ASPECTS OFx 4
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THEOVERRIDEOFC0WAINMENTPURGEVALVEISOLATIONT.T..?
.n LA. CROSSE BOILING WATER REACTOR 7
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1.0 INTRODUCTION
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.;.:. u Based on the information suppl'ied by the'Dairyland Power Cooperative-M." _
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(DPC),thisreportaddressestheelectrical,' instrumentation,An'ri. control systems design aspects of the Containment Ventilation Isolation (CVI) system and other related Engineered Safety Feature (ESF) functions for the La Crosse Boiling Water Reactor.
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Several instances have been reported where the automatic closure of the containment ventilation or purge isolation valves would not have occur-red because the safety actuation signals were manually overridden or blocked during normal plant operations. Lack of proper management con-trols, procedural inadequacies, and circuit design deficiencies contributed to these instances. These events also brought into question the mechanical operability of the valves themselves. These events were determined by the Nuclear Regulatory Commission (NRC) to be an Abnormal Occurrence (#78-05) and accordingly, were reported to Congress.
1 The NRC is now reviewing the electrical override aspects of contain-ment purging and venting for all operating reactors. On November 28, 1978, the NRC issued a letter, " Containment Purging During Nortnal Plant Opera-tion"I to all Boiling Water Reactor and Pressurized Water Reactor licensees. This required a review of these systems by the licensee.
DPC 2
3 responded on February.l., 1979. On February 20, 1981., DPC provided.
additional infennetion requested by the NRC. The Final Safety. Analysis.
Report (FSAR) and a letter of January 14, 1980,4 also contain design.
5' information reviewed for this report.
DPC comments of August 26, 198 1 were also evaluated _ for this report.
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1 a
f Guideline 6 in this rOview applies primarily to ctiher related ESF r
systems because implementation of this guideline for containment isolation will be reviewed by the Lessons Learned Task Force, based on therAcomen-
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dations iri NUREG-0578, Section 2.1.4.
When containment isolation is not involved, consideration on a case-by-case basis of automatic valve' reposi -
tioning upon reset may be considered acceptable. Acceptability would be
['
dependent upon sys'
.ction, design intent, and suitatile operating procedures.
2.2 Containment Ventilation ' Isolation Circuits Design Descfiption. -
The containment purge and vent isolation valves use solenoid-operated air pilot valves. Loss of power or air will cause the isolation valves to close. Automatic closure of the containment purge inlet and outlet isolation valves will occur on any of the following conditions :
1.
High reactor containment building pressure (5 psig).
2.
High primary system pressure (1325 psig).
3.
Low reactor water level.
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4.
High Radiation.
The four-inch vent header valve will also close on all of the above signals.5 During operation, these valves are closed.
DPC has indicated,
3 that these signals are derived from safety grade equipment. SEP Topic Ill-12, " Environmental Qualification," will vefify that they are.
The high primary system pressure signal can be bypassed for calibration by means of a tes+ switch on the front of the amplifier drawer of each channel. The amplifier drawers are located in the vertical control panel in the control room.
If both drawer test switches are in the " Test" position at the same't'ime, or if either switch is operated without first-operating the key operated scram bypass switch, a reactor scram will result.
The scram signal from each drawer cannot be bypassed at the same time. The use of either drawer test switch or the key operated scram bypass switch is annunicated.5 r..
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1 r s 2.4 Other Related Engin:cred Safcty Featura Systems Circuits. A r: view of other related ESF circuits was also made.
No other manual ove,rgides i
have been identified in the review of the material submitted '!oy this audit. -
3.0
SUMMARY
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The NRC issued a letter, " Containment' Purging During Normal Plant Operation," which requested DPC to review purging requirements, c'ontrols, and procedures for purging at the La Crosse station.
The electrical, instrumentation, and control design aspects of the containment ventilation isolation valves for La Crosse Unit I were evaluated using the design guidelines stated in Section 2.1 of this report. These guidelines are satisfied. However, automatic isolation will not occur for manual operation of the high pressure core spray or the alternate core spray systems. The NRC should determine if this is acceptable.
Both redundant CVI 20-inch valves are located inside containment.
This is not presently acceptable per General Design Criteria 56 which requires one valve to be inside containment and the other valve outside containment.
The NRC should determine the continued acceptability of this exemption to this General Design Criteria.
4.0 REFERENCES
1.
NRC/ DOR letter (A. Schwencer) to DPC and all BWR and PWR licensees,
" Containment Purging During Normal Plant Operation," dated November 28, 1978.
2.
DPC letter, F. Linder to the Director of Nuclear Reactor Regulation, NRC, " Containment Purging During Normal Plant Operation," February 1, 1979, LAC-6104..
i.
3.
DPC letter, F. Linder to the Director of Nuclear Reactor Regulation, NRC, " Bypass and Reset of Engineered Safety Features," February 20, 1981, LAC-7379.
4.
DPC letter, F..Linder to the Director of Nuclear Reactor Regulation, we-NRC, "IE Bulletin No. 79-08. Additional Information-Events Relevant to BWR's Identified During Three Mile Island Incident," January 14, T-1980, LAC-6732.
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