ML20198R196
| ML20198R196 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/29/1998 |
| From: | Gardner R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Walter MacFarland ILLINOIS POWER CO. |
| References | |
| NUDOCS 9901080122 | |
| Download: ML20198R196 (5) | |
Text
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p December'29, 1998
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Y Mr. Walter G. MacFarland IV-l Senior Vice President Clintcc. Power Station.
lilinois Power Company
' Mail Code V-275 g
l P. O. Box 678 :
j' Clinton,-lL 61727 b>
SUBJECT:
REQUEST FOR DOCUMENTATION FOR SAFETY SYSTEM ENGINEERING INSPECTION (SSEI)
Dear Mr. MacFarland:
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_ Starting on February 8,1999, NRC Region ill will be conducting a Safety System Engineering e
Inspection at the Clinton Power Station. This inspection will be performed in accordance with various NRC inspection procedures (IPs) including IP 93809, " Safety System Engineering Inspection," IP 37550, " Engineering," IP 37700, " Design, Design Changes, and Modifications,"
. and IP 92700, "Onsite Licensee Event Report Review."
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- These types of inspections have previously been found to be rather resource intensive. In order
- to eraure a productive inspection for both sides, we have enclosed a request for documents j'
needed for the inspection. These requests have been' divided into three groups. The first we would appreciate being mailed or faxed to Region lli as expeditiously as possible. This will allow the inspectors to determine which modifications and other engineering products they will review in more detail and allow your staff time to obtain copies of those modifications and supporting documents. The second group should be available to the NRC by January 19,1999. The team F
leader will arrange for a site trip to obtain the information. These documents will then be n
reviewed in the Region Ill office prior to the first onsite Inspection week. The final group of j
documents requested are procedures and other documents which the team will need access to
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during the inspection and should be available to the NRC by February 1,1999.
Attached to the list of requested documents is a list of items previously opened in NRC inspection reports or discussed in licensee event reports. We would appreciate it if you would review this list and determine which items appear ready for closure. The list should be marked
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. up with this information, along with the name of a cognizant hdividual and returned with the first set ofinformation.'
The team leader for this inspection is Eric Duncan. He can be reached at (630) 829-9739 if you have any questions about either the list or the inspection itself.
9901000122 981229 m
PDR ADOCK 05000461 G
C W. MacFarland. We appreciate your cooperation with this inspection Sincerely,
%$n $ar[n*dr,hhie Engineering Specialist Branch 2 Division of Reactor Safety Docket No.: 50-461 License No.: NPF-62
Enclosures:
- 1. Documents Requested for Safety System Engineering Inspection
- 2. Previously Opened items and Licensee Event Reports cc w/encis:
G. Hunger, Station Manager R. Phares, Manager, Nuclear Safety and Performance Improvement J. Sipek, Director - Licensing M. Aguilar, Assistant Attorney General G. Stramback, Regulatory Licensing Services Project Manager General Electric Company Chairman, DeWitt County Board State Liaison Officer Chairman, Illinois Commerce Commission Distribution:
RPC (E-Mai!)
Project Mgr., NRR w/encls J. Caldwell, Rlll w/encls C. Pederson, Rlil w/encls B. Clayton, Rllt w/encls SRI Clinton w/encls DRP w/encls TSS w/encls DRS (2) w/encls Rill PRR w/encls v; PUBLIC IE-01 w/encls
" Docket File w/encls 06'0005 GREENS IEO (E-Mail)
]
DOCDESK (E-Mail)
DOCUMENT NAME: G:\\DRS\\CL112298.wpd
- v. r.e.w.. con ome. accem.i. in o w c cm e===ve.
r. cm um awnvenew. u. % em OFFICE Rlli JM Rlli
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NAME Duncan:sd Gardner jb i
DATE 120'}/98 12/21/98 OFFICIAL RECORD COPY
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1 Documents Reauested for Safety System Enaineerina Insoection 1.
Idormation Reouested Exoeditiousiv The following general information is requested to be available to the NRC as soon as possible. This is necessary to facilitate the selection of items to be reviewed during the inspection so that sufficient time is available for the licensee to provide copies, j
List of programs within scope of Program Readiness Review.
List of degraded voltage modifications and changes.
List of electrical distribution changes.
List of electrical distribution calculations and setpoints.
The following specific information associated with the Reactor Core Isolation Cooling system is also requested to be available to the NRC as soon as possible.
List of all modifications performed en the system since initial plant startup.
List of all non-modification 50.59s and 50.59 screenings (excluding procedure revisions) performed on the system since initial plant startup.
List of all operability evaluations for the system since initial plant startup.
List of all condition reports for the system written over the last 5 years.
List of all calculations associated with the system.
List of all setpoint calculations and setpoint changes associated with the system.
List of all pre-operational tests performed on the system.
List of temporary modifications currently installed or installed within ine last 5 years on the system.
List of all open ac' ions requests (ARs) and work requests (WRs) for the system.
List of completed corrective maintenance activities over the last 5 years.
List of other engineering evaluations on the system since initial plant startup.
11.
Information Reauested by January 19.1999 The following general information is requested to be available to the NRC during a pre-inspection trip by the team leader on January 19,1999.'
Copies of modifications, temporary modifications, or setpoint changes, including j
associated 50.59 screenings or evaluations, selected by the SSEI team leader.
Copies of non-modification 50.593 and screenings, selected by the team leader.
Copies of operability evaluations selected by the SSEI team leader.
Copies of calculatior.s selected by the SSEl team leader.
Copies of engineering evaluations selected by the SSEl team leader.
SDFV package and supporting documentation associated with the AP system.
List of engineering self-assessments pcrformed within the last 24 months.
The following specific information associated with the Reactor Core Isolation Cooling system is also requested to be available to the NRC on January 19,1999.
Copies of preoperational tests selected by the SSEI team leader.
Copies of condition reports selected by the SSEl team leader.
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Supplemental AR/WR information selectad by the SSEI team leader.
List of operations procedures directly associated with the system.
List of all operating experience notifications and other industry and NRC correspondence re'ated to the system and the station response.
P&lDs, electrica' schematics, and other drawings associated with the system.
System Health Report data for the system.
Performance indicator data for the system.
Copy of vendor manual (s) associated with the system.
Certified pump curves for the system.
Gystem walkdown recordt.
List of periodic surveillance tests performed on the system.
Copy of completed operations-related and engineering-related surveillances completed in the last 5 years for the system (up to last 2 surveillances).
l Maintenance Rule data for the system.
l System Readiness Review package for the system.
I lil Information Reauested to be Available on Februgy 1.1999 l
We request that the following information be available to the team once it arrives onsite.
Copy of current organization chart.
Copy of Updated Final Safety Analysis Report (UFSAR).
Copy of Technical Specifications.
Copy of engineering procedures related to modifications, temporary alterations, safety evaluationa and screenings, calculation control, setpoint control, and setpoint methodology.
l List of all engineering-related procedures.
Copy of IPE/PRA report.
Copy of system engineering handbook or guidelines.
List of system and design engineers including assigned systems or design specialty.
List of pre-established engineering meetings.
Fuse control program review findings and corrective action information.
Generic Letter 96-01 review progress, findings, and corrective action information.
UFSAR review progress, findings, and corrective action information.
SDFV report (2 copies).
Post SDFV report (2 copies),
j Configuration Management Program Assessment and Update Review report.
Clinton Power Station Plan for Excellence (2 cop les).
Engineering backlog performance indicators for the last 12 months.
C&l Self-Assessment report.
P&lDs for all safety-related systems.
Restart Action item list.
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Previousiv Opened items and Licensee Event Reports l
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. The SSEI team would like to review the following items to determine if the issues have been resolved and corrective actions planned or completed such that the item could be closed, in order to facilitate this review, the team requests that " closure packages" be prepared that describe what actions were taken to resolve the issue and provide appropriate documentation to substantiate those actions (i.e. copies of procedures, training records, etc.) and that these l
closure packages be available at the site during the inspection.
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' Previousiv Opened items.
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.50-461/95003-03 URI Breaker Bulbs.
I' 50-461/97011-16 IFl Seismic Qualification of Circuit Breaker Cabinets.
50-461/97999-13 IFl Multiple EDSFI Open ltoms.
~ 50-461/97999-16 IFl GL 89-13 Preventive Maintenance items Not Reviewed.
j 50-461/97999-17 IFl Design Problems With Auxiliary and Offsite Power Systems.
50-461/98004-01 IFl Failure to Rely on Local Emergency Diesel Generator Indication.
50-461/98004-02 NCV inadequate Residual Heat Removal Fill and Vent Procedure.
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50-461/98004-03 NCV Inadequate Crew Briefing.
50-461/98004-04 NCV Fa!!ure to Evaluate Risk Prior to Maintenance.
50-461/98004-05 NCV inadequate Corrective Actions for NSPS Inverter.
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Licensee Event Reports 50-461/97007-00 LER -. Lack of Guidelines for Seismic Qualification of Breakers, i
50-461/97008-00 LER Emergency Diesel Generator Undervoltage Relays inoperable.
50-461/97010-00/01 LER Incorrect Voltage in Procedure Verification
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50-461/97028-00 LER Improperly Qualified 480-Volt Breaker Components.
50-461/97031-00 LER Inadequate Testing of Safety-Related Logic Circuits.
L 50-461/97034-00 LER Incorrect Cable Resistance and Brake Horsepower Data.
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50-461/98003-00/01 LER Loss of Division 2 NSPS loverter.
l 50 461/98006-00 LER incorrect Calculation in Diesel Generator Control C rcuitry.
I 50-461/98015-00 LER ESF Actuation Caused by Shorted Diode in the NSPS System.
50-461/98017-00 LER Misinterpretation of TS Regarding Battery Specific Gravities.
50-461/98021-00 LER Cracks in Medium and High Density Silicone Penetration Seals 50 461/98025-00 LER Failures of Switchgear Heat Removal Condensor Gasket.
50-461/98030-00 LER Insufficient Guppression Pool Makeup Volume to Meet Design 50-461/98032-00 LER Excessive Voltage Drop in Circuit for Division ll! DG Breaker.
50-461/98034-00 LER Suppression Pool Cooling Mode of RHR Inoperable.
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