IR 05000461/1986063
| ML20203N881 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 10/10/1986 |
| From: | Jablonski F, Neisler J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20203N878 | List: |
| References | |
| 50-461-86-63, NUDOCS 8610200094 | |
| Download: ML20203N881 (6) | |
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U.f.. NUCLEAR REGULATORY COMMISSION REGION III.
Report No. 50-461/86063(DRS)
Docket No. 50-461 License No. CPPR-137
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Licensee:
Illinois Power Company 500 South 27th Street Decatur, Illinois 62525 Facility Name:
Clinton Nuclear Power Station, Unit 1 Inspection At: Clinton Site, Clinton, IL Inspection Conducted:
September 23-25, 1986
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Inspector:
J. H. Neisler g
Datt Approved By:
. LJ o
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Date Inspection Summary Inspection on September 23-25, 1986 (Report No. 50-461/86062(DRS))
Areas Inspected:
Routine unannounced safety inspection of licensee Quality Assurance Program Administration, design change and' modifications,
. surveillance, QA Record, and test equipment controls.(35740), (35744),.
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(35745),(35748),(35750).
Results:
No violations or deviations were identified.
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DETAILS 1.
Persons. Contacted Principle Licensee Employees
- W. Gerstner, Executive Vice President
- D. Hall, Vice President
- K. Patter,on, Director, Material Management
- J. Fertic, Director, Quality Systems and Audits
- G. Bell, Assistant Manager, SOM
- R. Campbell, Manager, Quality Assurance
- J Penny, Manager, Nuclear' Programs Coordination
- J. Weaver, Director, Licensing
- J. Cook, Assistant Plant Manager
- J. Wemlinger, Supervisor, Operations Training
- K. Baker, Supervisor, I and E Interface R. Lebkuecher, Licensing J. Brownell, Licensing i
C. Hollon, Quality Assurance, Records J. Franke, Quality Assurance, Audits J. Taylor, Nuclear Records Supervisor A. Mueller, Quality Assurance J. Friend, Supervisor, Audits D. Majeres, Quality Assurance B. Williams, Calibration Laboratory Supervisor F.~ Oleander, Surveillance Coordinator
- Denotes those persons attending exit interview.
The inspector also contacted other site personnel in the engineering, quality assurance and document control areas.
2.
Quality Assurance Program (QA/QC Administration)
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The licensee's Quality Assurance Program defines the structures, systems,.
I components,. documents and activities to.which the program applies. The program identified testing, operations, maintenance and repair, refueling, modifications, radiological and environmental monitoring, radioactive material packaging and shipment, fire protection and security as applicable activities.
Applicable structures, systems and components are defined as those structures, systems and components listed in Table 3.2-1 of the Clinton FSAR.
To verify that procedures and responsibilities had been established, the inspector reviewed the licensee's quality assurance procedures, records
management procedures, and corporate nuclear procedures including:
QAP 105.01A05, Preparing and Revising, Quality Assurance Procedures l
QAP 105.01A10, Processing Advance Changes to Quality Assurance Procedures
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QAP 105.05 00cument Review
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QAP 118.07 Independent Audit of Illinois Power Quality Assurance Program In addition the inspector reviewed the 1985 overall QA Program Evaluation required by QAP 102.03. Weaknesses identified in the program were addressed and appropriate cnanges implemented to strengthen the program.
No violations or deviations were identified.
3.
QA Program:(Design Changes and Modifications)
The licensee has established procedures to control design changes ar.d modifications.
These procedures include methods for initiating changes, provisions for reviews and evaluations, responsibilities for design control and independent verifications, interfaces, approvals, drawing control, implementation of changes and modifications, and post modification and acceptance.
To verify that design and modification controls exist the inspector reviewed the following:
a.
Corporate Nuclear Procedures (CNP)
CNP 2.06,. Configuration Management, Revision No. 1, August 23, 1985 CNP 4.05, Plant Modification Program, Revision No. 1, October 14, 1985 CNP 4.08, Plant Modification System, Revision No. 0, October 14, 1985 CNP 4.13, Fire Protection Program, Revision No. 0, August 5, 1985 CNP 1.09, Nuclear Safety Reviews, Revision No. 1, June 17, 1986
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Nuclear Station Engineering Department Procedures D.20, Processing Plant Modifications, Revision No. 5, July 15, 1986 0.21, Processing Plant Modifications, (minor) Revision No. 1, i
June 11, 1986 i
i D.22, Engineering Interdisciplinary Review and_ Impact Assessment for l
Plant Modifications, Revision No. 7, September 5, 1986 l
l D.23, Plant Modification Supplement, Revision No. 3, August 26, 1986 l
D.25, Test Procedure Review and Approval for Plant Modifications, l
Revision No. 2, December 10, 1985
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D.26, Test Results Review and Approval for Plant Modification,
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Revision No. 4, August 8, 1985 l
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- I D.28, Cost and Feasibility Analysis and Conceptual Design, Rcvision~No.-4, July 15, 1986
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'D.29, Preliminary Design, Revision No. 4, July 15, 1986
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D.30, Final Design, Revision No. 4, July 15, 1986 D.33, Design Interface, Revision No. 0, July 15, 1986
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D.35, Design Control Program, Revision No. O,-July 15, 1986 D.36, Design Input', Revision No. 0, July 15, 1986 D.37, Design Verification, Revision No. O, July 15, 1986
D.38, Management of-Engineering Services, Revision No. O, June 13, 1986
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E.2, Safety Evaluation (Including 10 CFR 50.59 Safety Evaluations)
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Revision No. 3,' July 2, 1986
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-The inspector also reviewed Quality Assurance Instruction 305.02A13, Design. Document Review for Quality Requirement Revision No. O, October 9,
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1985 and Audit Reports Q38-86-31,.Q38-86-48 and Q-38-86-08, all relating
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to modifications and design control.
l No violations or deviations were_ identified.
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4.
-QA Program (Surveillance Testing and Calibration' Control)'
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.The inspector reviewed the master schedule for surveillance. testing and
calibration.
The schedule established frequencies for each activity, the
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plant group responsible for performing the activity, and the current
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. status of each test.
The licensee has a full-time surveillance coordinator whose j.
responsibility is maintaining the master surveillance test, calibration, and inspection schedule. The inspector reviewed 24
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completed tests that were included in the master schedule.
These tests were:
9382.01 125Vdc Battery Pilot Cell Check
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Main Stream Drain Valves Operability.
-9061.08
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i 9601.05C001.
Closed Fire Door Inspection
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9069.03 Shutdown Service Water Flow Path Verification
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9944.02 Reactor Water Conductivity Recorder Channel Check 9015.04 Standby Liquid Control Tank Heater Operability 9815.01 Diesel Fuel Oil System Pressure Test
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t 9281.05 Diesel Fuel Oil Cleanliness
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9910.72C001 Exhaust Duct PRM Calibration Check 9071.18 Fire Protection Hose House Equipment Visual Inspection for Safety Related Hydrants
9080.08 Diesel Generator Operability L
9053.03 ECCS Division 2 Operability 2210.01 Startup. Source Receiving, Handling, Storage, Inspection
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9061.07 Reactor Water Clean-up System Isolation Valve Operability 9213.01 Control Rod Drive Housing Support Visual Inspection 9431.13 Source Range Monitor C51-K600A, B, C and D Channel Calibration 9974.01 Sealed Source Contamination Leak Test 9437.14 Meteorology System Loop Calibration 9433.06 Reactor Vessel Water Level Channel Calibration 9831.01 Motor Operated Valve Overload Bypass Device Verification 9333.02 Division 2, 4.16KV Bus Undervoltage Relay Calibration 9275.03 Snubber Stroke Test 9382.07 Battery Capacity Discharge Test No violations or deviations were identified.
5.
QA Program (Records)
The licensee has established a records control program that requires the collection and maintenance of records of plant testing and operations, maintenance and modifications, safety committee meetings, procurement and receipt records, modifications and testing, design changes and drawings, nonconformances and deficiencies, personnel training and quality assurance audits, personnel qualification records and fire protection.
Responsibilities for records maintenance and storage have been assigned to the nuclear records supervisor. To verify the adequacy of the records control program, the inspector reviewed:
a.
Records Management Standards (RMS)
RMS Std. 1.01 Revision No. 1, January 29, 1986, Preparation and Control of Records Management System (RMS) Standards RMS Std 1.02, Revision No. O, October 9, 1985, Development of Required Record Lists (RRL)
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RMS Std 2.01, Revision No. O July 31, 1986, Standard for the Collection and Review of Records
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RMS Std 2.02,- Revision No. 2, July 31,1986, Standard for Records Quality RMS Std 2.03, Revision No. O, July 29, 1986, Disposition of Record
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Deficiencies RMS Std 3.02, Revision No. 2, August 26, 1986, Records Storage, Preservation and Maintenance RMS Std 4.01, Revision No. 0, January 13, 1986, Standard for the Receipt, Recording, Filing, Distribution and Maintenance of Controlled Documents RMS Std 3.01, Revision No. 1, July 31, 1986, Maintenance of the Clinton Power Station Records Classification Code List (RCCL)
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Corporate Nuclear Procedure, CNP 1.14, Revision No. 0, July 21,
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1986, Records Management No violations or deviations were identified.
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6.
QA Program (Measuring and Test Equipment)
The inspector ascertained by review of procedures and calibration records, interviews with calibration laboratory personnel and cognizant quality assurance auditors that the. licensee had established and implemented a program for the control of measuring and test equipment
(MTE).
Criteria and responsibilities for determining calibration frequency had been established.
Each device had a unique equipment identification j
number (EIN).
Before a piece of MTE can be used on site it-is sent to
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the calibration laboratory for validation and entry into the system.
i Calibration records were being maintained'on each device. -These records F
included the traceability to the calibration source, as-found and
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as-calibrated data, standards used for calibration, limitations (if any)
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on use, date of'last and next calibration and the person performing the
calibration.
Calibration standards were traceable to nationally recognized standards.
The. inspector reviewed two QA department audits involving MTE.
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Audit Q38-86-16 included MTE used by the electric shop and the control and instrumentation shop. -Audit Q38-86-25 included MTE used by the radiation environmental monitoring section.
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The plant has a central storage and issue point for MTE and each shop withdraws instruments for use in the shop. Using shops have storage areas
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for the MTE used by its personnel.
Calibration standards are the
responsibility of the calibration laboratory-supervisor.
Recall of equipment and review of previous use of equipment when a device
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is lost or found out of calibration is covered by MTE procedures. The
inspector verified by review of records of lost and out of calibration
equipment that the procedures had been implemented.
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No violations or deviations were identified.
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Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection and summarized the scope and findings of the inspection.
The licensee representatives acknowledged the
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inspector's comments.
The inspector also discussed the likely informational content of the inspection report with regard to documents
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or processes reviewed by the inspector during the inspection. The licensee did not identify any such documents / processes as proprietary.
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