IR 05000461/1993020
| ML20059A264 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/23/1993 |
| From: | Jeffrey Jacobson, Schapker J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20059A260 | List: |
| References | |
| 50-461-93-20, GL-88-01, GL-88-1, NUDOCS 9312300074 | |
| Download: ML20059A264 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION III
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~ Report No.~50-461/93020(DRS)
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Docket No. 50-461 License No. NPF-62 Licensee:
Illinois Power Company
500 South 27th Street Decatur, IL 62525 Facility Name: Clinton Power Station i
Inspection At:
Clinton, IL 61727 Inspection Condu,cted: October 6-7, 28-29, and December 1-2, 1993 f
Inspector:. [h.
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'f 4. F. Schapker Date
Approved q
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\\Jaterialhyd Processes Section
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Inspection Summary
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Inspection on October 6-7. 28-29. and December 1-2. 1993 (Recort No.
50-461/93020(DRS))
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Areas Inspected: Routine, announced inspection of inservice inspection activities including review of program (73051), procedures (73052),
j observation of work activities (73753), data review-and evaluation-(73755),
review of the erosion / corrosion program (49001),. and review of previously
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identified items (92701).
Results:
Of the areas inspected, no violations or deviations were identified.
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During the course' of the inspection, the following were noted:
The licensee. adequately deranstrated the ability to properly implement the inservice' inspection (ISI) program including Generic Letter (GL) 88-01, Augmented Inspection of Intergranular' Stress Corrosion Cracking (IGSCC) Susceptible Materials.
- The licensee's erosion / corrosion program use A sf-the-art computer i
codes and inspection techniques with continual u,
des.
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9312300074 931223-l PDR. ADOCK 05000461 i
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DETAILS
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Persons Contacted Illinois Power Company'(IP)
- J. Perry,-Senior Vice President
- J. Cook, Vice President and Manager, Clinton Power. Station
- J. Miller, Manager,- Nuclear System Engineering Department
- K. Graf, Director, Engineering Projects
- C, Huttes, Principal Assistant-
- J. Pruit, Nuclear. Assessor
- D. Morris, Director, Nuclear Assessment
- R. Wyatt, Manager, Nuclear Assessment
- J. Palchak, Manager, Nuclear Support Services
- J. Sipek, Supervisor, Regional Regulatory Interface
- R. Phares, Director, Licensing
- J. Lewis, Nuclear Program Analysis
- J. Langley, Director, Design and Analysis
- R. Frantz, Senior Licensing Engineer
- S. Bell, Supervisor, ISI T. Zwick, Project Specialist M. Desa, Senior Quality Verification Specialist Illinois Department of Nuclear Safety (IDNS)
- L. Sage,- Code Compliance Inspe. tor Factory Mutual Corocration (FMC)
W. Ruggles, ANII General Electric Company (GE)
E. Baley, Project Manager U. S. Nuclear Reculato'ry Commission (NRC)
P. Brockman, Senior Resident Inspector-F. Brush, Resident Inspector
- Indicates those present at the exit interview on December-2,1993.
Cther members of the plant staff and contractors were contacted and interviewed during the course of this inspection.
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2.
Review of Previously Identified items (92701)
i-(Closed) Unresolved Item (50-461/93003-03):
Inadeouate Testina of I
Diesel Generator Air Receiver Check Valves
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a.
Backaround-
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The NRC EDSFI inspection team noted that the safety related check valves, internal to the air start accumulators, were not being i
adequately tested. The licensee had submitted a Relief Request (to the.0ffice of Nuclear Reactor Regulation (NRR)) to perform testing of these valves via a system leak test during the monthly Emergency Diesel Generator (EDG)-operability surveillance. NRR
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approved the relief request; however, the system line-up during-the performance of the surveillance procedure did not isolate the safety related check valves from the nonsafety system. Therefore, the check valves, were not adequately tested because system t
pressure was not relieved in the functional direction of the check
valves.
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b.
Insnection
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The NRC inspector reviewed the licensee's corrective action taken
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to resolve the testing of the EDG air start accumulator check valves.
The licensee revised the applicable procedures to include isolation of the referenced check valves prior to performing the i
surveillance testing.
Review of the test data performed
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subsequent to the procedure revision confirmed the check valves functioned properly. The licensee's corrective action was
accepteble.
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3.
Inservice Inspection Proaram (73051)
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General (73051)
This was the second outage of the second period in the first ten-year plan. The licensee's ISI-plan conforms to the requirements
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of the ASME Boiler and Pressure Vessel Code,Section XI,1980 Edition, Winter 1981 Addenda. The services of an Authorized Nuclear Inservice Inspector (ANII) were procured and the ISI plan, procedures and personnel certifications had been reviewed by the
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ANIl.
Personnel from IP, WILY Laboratories, and GE perforrad the-151 in
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accordance with ASME Section XI.
GE performed reactor vessel weld
inspection utilizing the GERIS and GE SMART 2000 systems.
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licensee's inspection plan of IGSCC susceptible welds complies with the guidance in GL-88-01.
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Review of Procedures (730521 The NRC inspector reviewed procedures utilized during observation
of ISI work activities.
The ISI procedures were found to be in
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accordance with ASME Section V, 1980 Edition, Winter 1981 Addenda.
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The IDNS inspector reviewed the following procedures:
l Procedure Title GE-ADM-1006, R0 Procedure for Compliance with'NRC'RG
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l.150 GE-MT-100, R0 Procedure for Magnetic Particle
Examination (MT)
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GE-MT-101, R0 Procedure for Wet Fluorescent MT GE-PT-100, R2 Procedure for Color Contrast Liquid
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Penetrant Examination GE-UT-102, R3 Procedure for Manual Ultrasonic Testing (UT)- of Similar and
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Dissimilar Welds for IGSCC GE-UT-104, R1 Procedure for Manual UT Planer Flaw Survey GE-UT-106, R1 Procedure for Manual UT of Pressure
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Retaining Welds in Ferretic and Austenitic Piping and Components.
The procedures reviewed complied with applicable Code and
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regulatory requirements.
c.
Data Review (73755)
The NRC inspector reviewed documents related to nondestructive examination (NDE) equipment, NDE examiner certifications, NDE data and evaluations. The records reviewed complied with ASME Code and.
regulatory requirements.
The IDNS inspector reviewed the following repair and replacement packages:
MWR-D33023, Modification No. RT033: Modification to add a drain line to 1RT06D.
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MWR-D15233, Modification No. RF-4-46: Replace valve.
MWR-D26237, Modificatiori No. RF-4-47:
Modification of guide rails of a high pressure core spray valve.
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The repair and replacement packages were in compliance with the applicable Code and procedure requirements.
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d.
Observation of Work Activities (73753)
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The NRC inspectors observed work activities in progress and-
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interviewed personnel during the ISI activities. These-observations included the following:
'GE personnel performing ultrasonic. examination'(UT) on the-
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residual heat removal nozzle to reactor. vessel (RV) shell weld No. N6C and feedwater nozzle to RV shell weld No. N48.
These examinations were performed using the GERIS/GE SMART 2000 automated UT system.
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GE personnel performing UT of RV feedwater nozzle to safe end weld No. N4A-W-1 in accordance with the GL-88-01 guidelines.
IP personnel performing liquid penetrant examination on weld i
No. 1-0M-912-9Q2.
WILY inspectors performing functional testing-and VT-3 examination of the RHR system snubbers Nos.1RH07017; t
1RH07010; and IS3528 E-30.
Examinations and tests were performed in accordance with
applicable procedures and ASME Code requirements.
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4.
Erosion Corrosion Program (49001)
The licensee's erosion / corrosion (E/C) was formally implemented in 1987 in response to NRC Bulletin 87-01. Additional guidance from GL 89-08-and Electric Power Research Institute (EPRI) NP-3944 was added to the
program.
Special procedures and administrative controls were
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established to ensure continued long term implementation of the E/C
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monitoring program for piping and components.
The program is applicable to both safety and nonsafety related equipment. The program was established using state of the art EPRI Chec and Checkmate computer programs.
The NRC inspector reviewed the E/C program, procedures, and data records
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for this outage. The licensee's program was recently updated using industry experience, system engineering, operations experience, and
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EPRI's " Recommendations for an Effective E/C Program", draft report dated April 1992-The licensee plans to upgrade the E/C program to
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EPRI's CHECWORKS E/C computer program, when available, and complete requisite training. The licensee ultrasonically inspected 139 and visually inspected 3 components this outage.
The licensee's E/C program appears to be adequate to assure. flow accelerated E/C-is identified and monitored to prevent catastrophic failure of toth single phase and two phase components.
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' Exit Meetina:
n The NRC inspector met with licensee representatives.(denoted in Section
1) at the~ conclusion of the inspection on December 2,1993. The
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inspector summarized the scope and findings of the inspection
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activities. The licensee acknowledged the. inspection findings. The
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inspector. also discussed the likely informational content of the
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inspection report with regard to documents or processes reviewed by the inspector during the course of the inspection. The licensee did not
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identify any such document / processes as proprietary.
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