ML19338G488
| ML19338G488 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/17/1980 |
| From: | Thatcher D Office of Nuclear Reactor Regulation |
| To: | Satterfield R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19338G487 | List: |
| References | |
| NUDOCS 8010290418 | |
| Download: ML19338G488 (4) | |
Text
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l OCT 17 iggg MEMORANDUM FOR: Rodney M. Satterfield, Chief Instrumentation & Control Systems Branch M. Srinivasan, Section Leader k
Instrumentation & Control Systems Brangh)f THRU:
FROM:
Dale F. Thatcher Instrumentation & Control Systems Branch
SUBJECT:
SITE VISIT TO LASALLE COUNTY STATION The site visit by the members of the Instrumentation and Control Systems Branch to the LaSalle County Station is scheduled for October 29-31, 1980.
The proposed agenda for the visit is presented in the enclosure.
We propose to look at the areas listed and to also meet to discuss specific items.
At the conclusion of the site visit, we plan to meet with the applicant to summarize our findings and any necessary followup actions.
By copy of this memorandum, the LPM is requested to transmit this agenda to the applicant.
W
.a Dale F. Thatcher Instrumentation & Control Systems Branch
Enclosure:
As stated cc:
P. Check M. Srininsan A. Bour.1a g O
- d. KnJX F. Rosa R. Kendall R. Stevens
Contact:
D. Thatcher X29426 801029 0Tlf
GENERAL AGENDA
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INSTRUMENTATION & CONTROL SYSTEMS BRANCH LASALLE COUHTY STATION SITE VISIT 1.
Control Room and Instrumentation Cabinet Area a.
General layout b.
Nuclear and Reactor Protection instrument cabinet arrangement, layout sheidling, separation and identification.
c.
Rod position indication d.
Protection System initiation and bypassing arrangements (RG 1.47 recommendations ).
e.
Cabling in Control Room (separation, type, provisions).
f.
ESF Initiation and bypassing arrangements (RG 1.47 recommendations).
g.
RPS cabinets, Auxiliary Relay Cabinet - location of isolation devices.
2.
Cable Runs and Cable Spreading Area a.
General Layout b.
Implementation of Separation Criteria 3.
Vital Instrumentation and Control Power Supply Installation a.
General Layout b.
Physical and electrical separation (divisional).
c.
Potential for damage from fire, missiles, high energy line break etc.
d.
Monitoring instrumentation e.
Batteries 4.
Reactor Building, Auxiliary and Turbine Building a.
Protection system instrument arrangement - installation and environmental b.
Potential for instrument damage due to fire, missiles and pipe whip etc.
c.
Separation and independence of piping and wiring to redundant or diverse instruments.
d.
Provisions for testing protection instruments e.
Independence of safety buses 5.
Reactor Trip System a.
Rod drive power supplies
' ra= Discharge Volume & associated instrumentation ical and Electrical independence
..., ovisions for testing e.
Cabling and equipment identification f.
Back-up scram capability arid separation of redundant divisions
2 6.
ESF Systems and Pump Rooms a.
General arrangements b.
Physical and electrical independence (interlocks).
c.
Potential for damage due to fire, missiles, etc.
d.
Provisions for testing (initiation, actuation and final devices).
e.
Cabling for equipment identification.
7.
Instrument Piping a.
Physical separation b.
Potential for damage from missiles, flooding, pipe whip, etc.
c.
Test features d.
Specific - Scram Discharge Volume level sensors.
8.
Shutdown from Outside Control Room a.
Location of Shutdown Panel
- 1) Habitability it) Potential for damage from fire, missiles, flooding, pipe whip, etc.
b.
Identification of Controls.
9.
Cable Trace Verify the cable trace in the plant from sensor to final actuation devices on redundant RPS/ESF channels for a number of parameters - drywell pressure, reactor water level.
- 10. Other. Areas Reactor Core Isolation Cooling switchover circuitry Suppression Pool and Drywell Temperature Monitoring 11.
Owg Review & Discussion 1.
Automatic Depressurization System / Safety-Relief System ir.cluding
. Low-Low Septpoint Relief Logic 2.
Primary Containment and Reactor Vessel Isolation Control System.
3.
High Reactor Water Level Cutot '
4.
Test Procedures requiring fuse pulling.
5.
Recirculation Pump Trip - ATWS 5.
Main Steam Isolation Valve - Leakage Control System
MEETING
SUMMARY
DISTR,IBUTION G. Lear NRL POR V. Noonan Local POR S. Pawlicki TIC /MSIC/ Tera V. Benaroya NRR Reading Z. Ros:toczy LB#1 Reading W. Haass H. Denton D. Muller E. Case R. Ballard D. Eisenhut W. Regan R. Purple D. Ross B. J. Youngblood P. Check A. Schwencer R. Satterfield F. Miraglia
- 0. Parr J. Miller F. Rosa G. Lainas W. Butler R. Vollmer W. Kreger J. P. Knight R. Houston R. Bosnak T. Murphy F. Schauer L. Rubenstein R. E. Jackson T. Speis Project Manager ABournia W. Johnston Attorney, OELD J. Stol:
M. Rushbrook S. Hanauer OIE (3)
W. Gammill ACRS (16)
R. Tedesco F. Schroeder D. Skovholt M. Ernst NRC Particicants:
R. Baer C. Berlinger D. Thatcher, R. Stevens and K. Kniel
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R. Kendall G. Knighton a ani D.{iondi CEC 0
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L. Del George D. Vassallo P. Collins D. Ziemann bcc: Applicant & Service List