ML20132G044
| ML20132G044 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 07/10/1985 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | Spangenberg F ILLINOIS POWER CO. |
| References | |
| NUDOCS 8507190140 | |
| Download: ML20132G044 (7) | |
Text
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Docket No. 50-461 DISTRIBUTION Docket < File JPartlow NRC PDR BGrimes Local PDR EJordan Iir. Frank A. Spangenberg PRC System RKendall Director of Nuclear Licensing &
NSIC FRosa Configuration Management LBf2 reading Clinton Power Station BSiegel P.O. Box 306 EHylton Mail Code V920 Goddard,0 ELD Clinton, Illinois 61727 ACRS (16)
Dear Mr. Spangenberg:
SUBJECT:
INSTRUMENTATION AND CONTROL SYSTEMS BRANCH SITE VISIT AGENDA FOR CLINT0ll The Instrumentation and Control Systems Branch (ICSB) has proposed July 29, 30, and 31, 1985 for a site visit to Clinton. The enclosure contains the agenda i
items that have been selected so that the staff can evaluate the implementation of I&C systems for both standard ICSB review areas (e.g., physical separation between redundant safety related circuits within instrument cabinets), and special interest areas addressed during the licensing review. The site visit
.will concentrate on those areas which will aid in resolving outstanding and confirmatory. issues listed in Chapter 7 (Instrumentation and Controls) of the SER and issues resulting from the CAT inspection.
Please contact your project manager.by July-19 regarding the acceptability of the proposed dates for the site visit or on any other matters regarding this visit.
Sincerely, Original signed by Walter R. Butler, Chief Licensing Granch No. 2 Division of Licensing
Enclosure:
As stated cc: See next page i
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JUL 101985 Docket No. 50-461 Mr. Frank A. Spangenberg Director of Nuclear Licensing &
Configuration Management Clinton Power Station P.O. Box 306 Mail Code V920 Clinton, Illinois 61727
Dear Mr. Spangenberg:
SUBJECT:
INSTRUMENTATION AND CONTROL SYSTEMS BRANCH SITE VISIT AGENDA FOR CLINTON The Instrumentation and Control Systems Branch (ICSB) has proposed July 29, 30, and 31, 1985 for a site visit to Clinton. The enclosure contains the agenda items that have been selected so that the staff can evaluate the implementation of I&C systems for both standard ICSB review areas (e.g., physical separation between redundant safety related circuits within instrument cabinets), and special interest areas addressed during the licensing review. The site visit will concentrate on those areas which will aid in resolving outstanding and confirmatory issues listed in Chapter 7 (Instrumentation and Controls) of the SER and issues resulting from the CAT inspection.
Please contact your project manager by July 19 regarding the acceptability of the proposed dates for the site visit or on any other matters regarding this visit.
Sincerely, Walter R. Butler, Chief Licensing Branch No. 2 Division of Licensing
Enclosure:
As stated cc: See next page
Mr. Frank A. Spangenberg Clinton Power Station Illinois Power Company Unit 1 cc:
Mr. Allen Samuelson, Esquire Jean Foy, Esquire Assistant Attorney General 511 W. Nevada Environmental Control Division Urbana, Illinois 61801 Southern Region 500 South Second Street Richard B. Hubbard Springfield, Illinois 62706 Vice President Technical Associates Mr. D. P. Hall 1723 Hamilton Ave. - Suite K Vice President San Jose, CA 95125 Clinton Power Station P. O. box 678 Clinton, Illinois, 61727 Nr..H. R. Victor Manager-Nuclear Station Engineering Dpt.
Clinton Power Station P. O. Box 678 Clinton, Illinois 61727 Sheldon Zabel, Esquire Schiff, Hardin & Waite 7200 Sears Tower 233 Wacker Drive Chicago, Illinois 60606 Resident Inspector U. S. Ruclear Regulatory Commission RR 3, Box 229 A Clinton, Illinois 61727 Mr. R. C. Heider Project Manager Sargent & Lundy Engineers 55 East Monroe Street Chicago, Illinois 60603 Mr. L. Larson Project Manager General Electric Company 175 Curtner Avenue, N/C 395 San < Jose, California 95125 Regional Administrator, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
Enclosure t
INSTRUMENTATION AND CONTROL SYSTEMS BRANCH SITE VISIT AGENDA FOP.CLINTON 1.
Control Room a.
Review the nuclear system protection system (NSPS) instrument cabinet wiring (identification of safety related and associated circuits, physical separation provided between redundant safety related circuits an:f between safety related and non-safety related circuits, isolation provided for interdivisional wiring, etc.).
b.
Review the internal wiring of the main control boards and control room back row panels (physical separation between redundant safety related circuits and between safety related and non-safety related circuits, e.g., control and annunciator circuits).
c.
Review the PGCC floor sections (metal barriers) used to provide physical separation between redundant safety related circuits and between safety related and non-safety related circuits.
d.
Review all reactor vessel water level indication provided (indi-cators and recorders; their ranges', safety classification, power supplies,etc.).
e.
Review the safety relief valve position indication required by TMI Action Plan Item II.D.3.
~
f.
Review the containment pressure, water level, and hydrogen con-centration instrumentation required by TMI Action Plan Item II.F.1 (4), (5), & (6).
g.
Review the interfaces between the NSPS and the self test system (STS), and the capability for manually testing NSPS circuits in-dependent of the STS (i.e., channel checks, channel functional I
tests, and channel calibrations).
Review how plant personnel inter-face with the STS via the plant computer using the diagnostic terminal to isolate STS detected faults and to control the STS.
h.
Review ADS instrumentation, including the ADS inhibit switches and the high drywell pressure bypass timers installed to satisfy l
the requirements of TMI Action Plan Item II.K 3.18.
i.
Review the scram discharge volume high water level trip bypass switches and associated annunciation.
4 J.
Review the RPS/NS divisional bypass switches arid associated indication / annunciation, k.
Review the CAM system panels and alarms.
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. 1.
Review the indication / annunciation provided for the following:
1.
Transfer of control to the remote shutdown panel.
2.
ECCS injection valvet low pressure permissive.
3.
RPS sensor trip annunciators.
4.
STS detected failures.
5.
ADS 105 second timers initiated and ADS out of service.
6.
Shutdown from Outside the Control Room a.
Walk from the control room to the remote shutdown panel along the path to be taken by the operators in the event of centrol room evacuation.
.. b.
Review the instrumentation provided at the remote shutdown panels, and the locations of the transfer switches.
Review the remote shutdown panel internal wiring (separation c.
between safety related and non-safity related circuits).
d.
Review how a reactor trip may be accomplished from outside the control room.
e.
Review the operation of Division 2 equi nt used to achieve reactor shutdown from outside the control room Division 1 power is assumed tobeunavailable).
3.
Reactor Building, Auxiliary Building, and Turbine Building Review the safety relief valve (SRV) accoustic monitors installed a.
on the SRV discharge lines.
b.
Review the.NSPS/RPS pcwer supplies (120 Vac RPS buses, inverters, batteries, and chargers; 125 Vdc divisional batteries; 24 Vdc logic power supplies).
Review the scram discharge instrument volume and associated c.
instrumentation, d.
Review the ESF pump rooms (HPCS, RCIC, RHR, LPCS).
Review the instrumentation (instrument lines, transmitters, and e.
associated circuits) used to provide the low reactor pressure permissive interlock function for the redundant low pressure ECCS systems (for both injection valves and the suction valves from the recirculationloop).
j 1
. f.
Review the following plant equipment:
1.
ADS solenoids.
2.
MSIV solenoids.
3.
Diesel generators and local control capability.
4.
Backup scram valves.
5.
Cable spreading area.
6.
Main steamline flow and radiation sensors.
7.
CAM system local panels and sampling points.
8.
Recirculation pumps, motors, supply breakers (from both 6.9 KV and the LFMG sets), and breakers used to accomplish both EOC and ATWS recirculation pump trips.
9.
Instrumentation used to transfer RCIC and HPCS suction from the RCIC storage tank to the suppression pool on storage tank low level.
- 10. HCUs.
4.
Circuit Traces Trace the circuitry (from sensors to protection system cabinets) a.
used to transfer HPCS and RCIC pump suction to the suppression pool on low RCIC tank temperature or low suction piping temperature.
b.
Trace the circuitry (from sensors to actuated equipment) used to isolate the normal intake dampers and initiate the control room HVAC system on high radiation measured at the outside air intakes.
5.
Local Instrument Racks / Piping Review the physical separation between and the routing of redundant a.
reactor vessel level and drmll pressure instrumentation (from vessel taps to transmitters).
b.
Review the turbine first stage pressure instrument taps, sensing lines, and transmitters.
,..* ~
6.
Capability for Testing a.
Walk through the planned testing procedures (channel functional tests, logic tests, etc.) for automatic and manual testing of typical NSPS instrument, logic, and actuation channels, and the surveillance planned for the STS to ensure that it is functioning properly.
- These items should receive priority.
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