ML20094B929
| ML20094B929 | |
| Person / Time | |
|---|---|
| Issue date: | 11/24/1975 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-07-A7-B, NUREG-75-87, NUREG-75-87-7-A7-B, SRP-07-APP-7-B, SRP-7-APP-7-B, NUDOCS 9511010363 | |
| Download: ML20094B929 (4) | |
Text
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p Kro NUREG 75/087 p
U.S. NUCLEAR REGULATORY COMMISSION gr O
1 STANDARD REVIEW PLAN OFFICE OF NUCLEAR REACTOR REGULATION APPENDIX 7-B GENERAL AGENDA. STATION SITE ISITS An important part of the review at the operating license stage is a site visit. It is prefer-able to have the site visit sometime before the completion of the drawing review. The purpose of the site visit is to supplement the review of the design based on the drawings and to evaluate the actual implementation of the design as installed at the site. The Regional Office of Regu-latory Operations having jurisdiction over the plant under consideration should be notified ahead of time of the visit so that the regional inspectors can become familiar on a first-hand I
basis with findings that may require followup action. Since proper implementation of design is the ultimate goal of the technical review process. the importance of a site visit is self-evident. The following is a typical general agenda that may be used as a guide for developing a specific agenda for the plant under review.
1.
Preliminary Discussions a.
U#.. w olved items, b.
Plant layout for touring.
c.
Special interest areas.
2.
Control Room a.
General layout.
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b.
Nuclear and reactor protection instrument arrangement and layout, c.
Rod position indication.
d.
Protection system initiation and bypass switcii orroi.gements.
e.
Diesel control board, f.
Cabling in control room (separation loading. etc.).
g.
Radiation monitoring.
h.
Engineered safety feature initiation and bypass switch arrangements and status panels.
3.
Cable Runs and Cable Spreading Area a.
General layout.
b.
Degree of separation.
c.
Diverse wiring.
d.
Tray or wireway density (percentage fill).
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e.
-Fire detection and prot 5ction.
f.
P2netrations and cable terminations.
1 4.
Switchgear Rooms a.
General layout.
b.
Physical and electrical separation of redundant units.
c.
Potential for damage due to fire, missiles, etc.
d.
Cable installation.
e.
Fire detection and protection.
5.
Battery Installations a.
General layout, b.
Physical and electrical separation, c.
Potential for damage due to fire, missiles, etc.
d.
Fire detection and protection and security.
f e.
Ventilation independence.
f.
Monitoring instrum mtation.
1 6.
Diesel Generators a.
General layout.
b.
Physical and electrical separation of redundant units.
c.
Fuel supply system.
d.
Fire detection and protection, e.
Qualification tests - interlocks and control panel, f.
Auxiliary systems - starting air, combustion air. ventilation.
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7.
Instrument Piping a.
Physical separation and single failure, l
b.
Potential for damage due to fire, flooding, etc.
c.
Test features.
8.
Transformers (Switchyard) a.
Physical and electrical separation, b.
Potential for damage due to fire, flooding, missiles, etc.
c.
Fire detection and protection.
9.
Quality Control Onsite receipt, storage, installation,and protection procedures of installed a.
instrumentation, equipment, and cables.
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10.
Reactor Building and Turbine Building a.
Protectiot system instrument arrangement and layout.
b.
Potential & instrument damage due to fire, missiles, etc.
Separation of piping and wiring to redundant instruments.
c.
d.
Provisions for testing protection instruments.
7B-2 i
I 11.
Shared Systems for Multi-Unit Sites a.
Equipment location and potential for damage, b.
Control room control and assignment to accident unit.
c.
Availability upon completion of first unit.
v 12.
Steam Lines - Main HPCI, RCIC a.
BWR temperature and radiation monitoring systems.
b.
Isolation valves.
13.
Recirculation Water System (Condenser) a.
Break detection and flood protection features.
14.
Shutdown Outside Control Room a.
Location for potential damage.
b.
Feedwater system, etc.
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