ML19207B415
| ML19207B415 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 07/31/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Linder F DAIRYLAND POWER COOPERATIVE |
| References | |
| NUDOCS 7908290114 | |
| Download: ML19207B415 (5) | |
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UMTED STATES y
o, NUCLEAR REGULATORY COMMISSION y'
g WASHINGTON, D. C. 20555
-y July 31,1979 k..... p#
Docket No. 50-409 Mr. Frank Linder General Manager Dairyland Power Cooperative 2615 East Avenue Souti.
Lacrosse, Wisconsin 54601
Dear Mr. Linder:
MODIFICATION OF REQUESTS FOR ADDITIONAL INFOR
SUBJECT:
NRC STAFF REPORT ON BOILING WATER REACTORS letter to you we requested that you provide certain In our July 17, 1979 information which we require for our generic report on boiling water reactors This information was broken down into two areas, i.e., system and (BWRs).
analysis.
As a result of a recent meeting with tb General Electric BWR owners group we agreed to modify some of our informa ion needs as well as the schedule These modifications are set for utilities to provide that informatica.
forth below:
The information requirements in Table II of Enclosure 1 to our (1 )
letter and submittal date therefor have been July 17,1979 The Enclosure to this letter defines the scope changes and lists that information that is to be provided by August 17, modified.
The remaining information in Table II of Enclosure 1 to 5
1979.
letter is to be provided not later than our July 17, 1979 November 16, 1979.
The information requirements in Attachment 2 to Enclosure 1 of t
letter and submittal date taerefor have been (2) our July 17, 1979 modified as follows:
submittal the information required For the August 17, 1979 for Item I should be limited to the identification of those (a )
lines which could potentially transfer radioactive liquids and gases out of containment and a description of the diversity of the containment isolation signals for these The remainder of the information in Item I should lines.
be provided not later than November 16, 1979.,
857 248 79 08290 //f
July 31,1979
- Mr. Frank Linder The information requested in Item iia is to be provided 16, 1979 to the extent it was not (b) not later than November previously provided in response to I&E Bulletin 79-01.
The information requested in Items IV thru VI should be (c) provided not later than November 16, 1979.
Item I of Attachment 3 to Enclosure 1 of our July 17 letter has (3) been modified as follows:
Do procedures exist for loss of feednater and small break LOCA for the cases of (1) all a.c. power available, (2) loss of offsite power, and (3) loss of all a.c. power?
If you require any clarification of the matters discussed in this letter please contact William F. Kane (301) 492-7745.
Sincerely, f
/N
,4'W W 33 %
Dennis L. Zieman, Chief Operating Reactors Branch No. 2 Division of Operating Reactors l
. July 31,1979 4
Mr. Frank Linder cc w/enclosare:
Fritz Schubert, Esquire Staff Attorney Dairyland Power Cooperative 2615 East Avenue South La Crosse, Wisconsin 54601
- 0. S. Heistand, Jr., Esquire Morgan, Leuis & Bockfus 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 La Crosse Public Library 800 Main Street La Crosse, Wisconsin 54601 I
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250 8 57 I
ENCLOSURE TABLE II SHORT-TERM Infonnation on Systems Capable of Providing Post-Accident and Transients Core Cooling General System Design Infomation Aretheinstrumentsandequipmentaffectedbycor.tainmentflooding(Yes/N Nomal position of valves, indication location, direct.or indirect indications.
Failed state of each. yalye.
Power sources required for system operation (including support systems).
Number of safety and relief valves, relieving capacity, cycling capability Are there alternate air supplies?
(number of times withoui. air supply).
Relief and safety valve setpoints.
System trips.
Are auxiliary systems required for operation? (Yes/No)
If yes, what are they?
System Activation Automatic startup logic (initiation signals) and power source (AC/DC).
Auto initiation built-in time delay (Yes/No)? If yes, what is time required?
Can manual initiation of the system be done in the control room? (Yes/No) if no, what actions are required and how long will they take?
Do ECCS initiation signals override all other modes of operation? (Yes/No)
If no, identify.
Are actions perfomed by the operator for system operation and control after initiation of the system? (Yes/No)
If yes, explain (up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)?
l Are there system interlocks and diversion for systems in Table I? (Yes/No) i If yes, explain.
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857 lI
Enclosure Water Sources Primary water source, total and dedicated capacity.
Secondary and backup water sources, auto / manual, are these proceduralized?
(Yrs /do). What is the time required for manual operation?
Are there strainers in system? (Yes/No)
If yes, give location and size (fine / coarse).
Power Source Number of trains.
For the following, assume a loss of feedwater, stuck-open relief valve, and explain the operator action necessary for core cooling considering multiple system failures.
All A-C available - operator action,- time required?
Loss of offsite power - operator action - time required?
Loss of all A-C - operator action - time required?
(assume both HPCI, RCIC or 1so. Cond. available)
Instrumentation and Control Automatic and manual control from control room (Yes/No)?
Do the alams in the control room give the operator the system status? (Yes/No)
Are system flow paths indicated in the control room (pump, valves, level, flow, press temp)? (Yes/No)
Remote control panels (Yes/No)
If no, explain.
Methods for detecting leaking safety / relief valves (i.e., leaking bellows, unseated valve)?
I Testing / Technical Specifications i
out of service Limiting conditions for operation (Matrix showing systemt with time)?
Is the method of verification of correct test lineup and restoration to normal condition proceduralized? (Yes/No)
Is the, an independent verification?
(Yes/No) By whom?
Is there system and component testing following maintenance? (Yes/No) i Aside from those systems normally in service, identify any component not ll nomally tested.
!I 857 252 (i
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