ML20213E342
| ML20213E342 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/02/1983 |
| From: | Rosa F Office of Nuclear Reactor Regulation |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0569, CON-WNP-569 NUDOCS 8303110315 | |
| Download: ML20213E342 (5) | |
Text
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.fL lIJ MSiORANDUM FOR:
Al Schwencer, Chief, Licensing Branch f2 Division of Licensing FROM:
Faust Rosa, Chief, Instrumentation & Control Systems Branch Division of Systems, Integration
SUBJECT:
IfiSTRUMENTATION AtiD CONTROL SYSTDiS BPANCH SITE VISIT AGEllDA FOR WHP-2 Plant Itame: WNP-2 Docket tio.: 50-397 Licensing Status: OL
., J, f Responsible Branch: LB J2 C.runa *
.m Project !!anager:
R. Auluck
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Review Branch: ICSB Review Status:
Incomplete Enclosed is the Instrumentation and Control Systens Branch (ICSD) planned site visit agenda for WNP-2. The ICSB site visit is currently scheduled for April 26, 27, and 28,1983. This agenda should be famcrded to the applicant far enough in advance of the site visit to allow sufficient time to plan plant walk-throughs to access these areas of interest to the staff. The agenda items have been selected such that the staff can evaluate the actual imple-mentation of the design as installed at the site for both standard ICSD re-view items and special interest items addressed during the licensing review.
Please contact Rick Kendall on X29451 if you have any questions regarding this egenda.
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Faust Rosa, Chief Instrumentation & Control Systems Branch Division of Systems Integration
Enclosure:
DISTRIBUTI0ti:
As stated ICSB R/F cc:
R. !!attson R. Kendall (PF) (2)
R.W. Houston C. Rossi T. Ilovak WtiP-2 Subject File R. Auluck it. Chiramal
Contact:
rendall, ICSB ICSB/DSI' 3058/Of[
ICSB/DSI.
RKendall :chCG6ssi (
FRosa 031103t[83 02Y/1
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j TNSTRUMENTATfCN AND CONTROL SYSTEMS BRANCH i
j SITE VISIT AGENDA FOR WNP-2 l
1.
Preliminary Discussions l
a.
Dist.ussion of plant layout (from drawings) and general plant tour.
i b.
Briaf identification of outstanding issues.
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c.
Brief overview of the station distribution system from one line j
diagrams (4160, 480, & 120 Vac, and 125 Vde).
I d.
Discussion of physical separation requirements applicable to WNP-2.
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2.
Centrol Room a.
Review general layout of the control room.
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b.
Review annunciation provided when the ECCS low pressure permissive
,i (high pressure / low pressure interlock) is satisfied.
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c.
Review the layout of the RPS and ESF instrument cabinet internals i
(identification of safety and associated circuits, separation between redundant circuits, and isolation provided for interdivisional wiring).
f-d.
Review the internal wiring of the main control boards (physical
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separation between redundant safety circuits and between protection j
systems and control and annunciation circuitry).
1 e.
Review annunciation provided upon transfer to the remote shutdown panel.
f.
Review the safety relief valve (SRV) position indication resulting l
from TMI Action Plan item !!.D.3.
i g.
Review the control rod position indication, b.
Review the recirculation flow instrumentation shared by the redundant RBM channels (specifically, the armored / shielded cable which penetrates 3
the fire barrier between RBM channels).
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2 i.
Review RBM data bus runs.
j.
Review the RBM bypass switch (separation'between channels).
k.
Review the containment pressure, water level, and hydrogen concentration instrumentation; TMI Action Plan Item II.F.1 (4), (5), and (6).
1.
Review annunciation for scram discharge volume (SDV) high level trip bypass and the me.thod used to effect this bypass (keylock switches),
m.
Review Standby Liquid Control System initiation and associated alarms (high and low solution temperature and tank level).
n.
Review all ranges cf reactor vessel water level instrumentation provided (indicators and recorders).
o.
Review the bypassed and inoperable status indication provided for the RPS, ESF systems, and other systems required for safety.
3.
Shutdown from Outside the Control Poom a.
Review how reactor trip may be accomplished from outside the control room, b.
Review location of transfer switches, c.
Walk through the' expected remote shutdown scenario (from control room to the remote shutdown panel) and observe the instrumentation and controls used to effect shutdown of the reactor.
d.
Review remote shutdown panel internals, e.
Review the remote shutdown panel location, accessibility, and habit-ability. (ventilation provided),
f.
Review location (s) from which shutdown is effected given a loss of division 1 power at the remote shutdown panel.
d 4.
Reacior 5uilding, Auxiliary Building, and Turbine Buildino a.
Review the safety relief valve (SRV) accoustic monitoring instrumentation installed as a result of TMI Action Plan Item II.D.3.
b.
Review the RPS M-G Sets and their associated electrical protection assemblies (EPAs).
c.
Review the scram discharge instrument volume and associated instrumentation.
c d.
Review 120 Vac and 125 Vdc emergency buses (chargers, batteries, inverters,etc.)
e.
Review ESF pump rooms (HPCS, RCIC, RHR, LPCS) and local start capability.
f.
Review the following plant equipment:
ADS valves and solenoids.
' '. Diesel' generators (including storage tanks, trans.fer pumps, and local control).
SLCS pumps, explosive squib valves, and boric acid ' tank j
Shutdown Service Water pumps and instrumentation.
5.
Circuit Traces a.
Trace redundant channels of protection system circuitry used to l
trip the reactor on turbine stop or governor valve position (from the limit switches or pressure switches to the RPS cabinets).
t b.
Trace the instrument piping and associated circuits used for the high I
pressure / low pressure interlock function for redundant icw pressure-ECCS systems.
This sho$1d include. interlocks for, both'the suction 7
valves from the recirculation lines and the injection valves.
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c.
Trace the circuitry (from sensors to protection system cabinets) used to transfer HPCS and RCIC pump suction to the suppression pool on CST low level.
1 6.
Loccl Instrument Racks / Piping a.
Review separation between redundant reactor vessel level instrumentation (from vessel taps to transmitters).
b.
Review turbihe first stage pressure instrument taps and transmitters.
7.
Capability for Testing Walk through the planned testing procedures (channel functional a.
tests, logic tests, etc.) for RPS and or ESF system instrument and logic channels.
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