IR 05000461/1981028
| ML20038B542 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 11/18/1981 |
| From: | Danielson D, Erb C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20038B535 | List: |
| References | |
| 50-461-81-28, NUDOCS 8112080384 | |
| Download: ML20038B542 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION
. REGION.III Report-No. 50-461/81-28 Docket No. 50-461 License No. CPPR-137 Licensee:
Illinois Power Company
.500 South 27th Street Decatur,.IL 62525 Facility Name:
Clinton Power Station, Unit 1 Inspection At: Clinton Site, Clinton, IL Inspection Conducted: October 26-29, 1981
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. Inspector: 4. M. Erb Approved By: D
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Materials and Processes"Section Inspection Summary Inspection on October 26-29, 1981-(Report No. 50-461/81-28)
Areas Inspected: Inspection of suppression pool floor and quenchers installation; QA' documentation'of certain safety related pumps and valves; inspection of hardware and documentation for containment penetrations; previously identified inspection findings. This inspection involved a
. total.of 25 inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviation were identified.
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8112080384 811155
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PDR ADOCK 05000461
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DETAILS Persons Contacted l
Licensee Employees
- J.-O. McHood, Vice President, Project Manager
- M. C. Hollon, Supervisor, Construction-QA
- L. Dozier, Assistant Director Construction
- R. J. Canfield, Assistant Director Construction
- E. E. Connon, Director Compliance
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- M. E. D' Haem, Supervisor QA-Operations R. W..Morgenstern, QA Engineer Other Personnel
- J. W. Smart,'QA Manager, Baldwin Associates (BA)
- W.'Harrington, Project Manager (BA).
- L. A. Gelbert, Manager, QC (BA)
- T. Selva, Manager Quality and Technical Services (BA)
- G. A. Chapman,Ifanager Technical Services (BA)
- H. R. Swift, Project Engineer (BA)
- S. J. Hall, Quality Control, General Electric (GE)
M. West, General Foreman, Pipe Fabrication (BA)
J. Corley, Foreman (BA)
D. Peterson, QA Supervisor, Chicago Bridge and Iron (CBI)
NRC'- Region III
- H. Livermore, Senior Resident Inspector
- Denotes those present at the exit interview.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (461/81-13-01): When tensioning the 120 hold down studs for the reactor vessel, non-uniform load results were found,with a.
given stud extension. The licensee agreed to check 60 of the bolts to determine if the heat treatment were acceptable. Teledyne have completed
'these hardness checks for IPC and the inspector has seen the 'results and agrees that acceptable hardness exists in these studs.
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Functional or Program Areas Inspected 1.
Observations of Work in the Suppression Pool a.
Sixteen quenchers have been installed and this completes the SRV requirements. The welds of the quencher base to the floor plate
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and the first circumferential weld above the floor plate were inspected for Quenchers Identification No. 1 MS-22017A, 1 MS-2101*A and 1 MS-31014A. The base weld showed proper reinforcement and
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was ground to a smooth finish.
These welds had an acceptable appearance b.
Extensive rework is being performed by Chicago Bridge and Iron (CBI) on the suppression pool floor because of pitting.
For months, water laid in the suppression pool and apparently this contaminated water caused pitting in the type 304 stainless floor plates and the leak chase channels.
The foreman for CBI said that pits were up to 3/16"' deep. The floor plates are 1/2" thick and the leak chase channels are 1/4" thick.
The pits are being filled using the manual metal are process followed by flush grinding. The repaired area will then be liquid penetrant tested and also be given a vacuum box test.
No items of noncompliance or deviations were identified.
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Documentation for Safety Related Pumps and Valves a.
Documentation on the following pumps was examined.
System Ident.
PQC Mfr.
Class LPCS E21-C001 BB843 B-J
HPCS E22-C001 DD790 B-J
RHR E12-C002 DD812 B-J
The certifications, NDE records, dimensions, heat treat records, avl test reports were acceptable for the above pumps. The pumps met S&L specification K-2801 and ASME Section III, 1971 Edition, Summer 1973 Addenda, b.
Documentation of safety related valves was examined as follows:
System Ident.
Class Mfr.
14" RHR IE12F029C
Anchor Darling Gate 14" HPCS E22F024
Anchor Darling Check 4" LPCS E21-F302
Anchor Darling Gate The documentation was complete for the above valves and all required code information was included. These valves were made to the requirements of ASME Section III, 1974 Edition, 1975 Addenda plus Code Cases 1516.1, 1567, 1622, 1635-1, and 1677.
No items of noncompliance or deviation were identified.
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Process Pipe Penetration Welds on several penetrations were inspected and the appearance was acceptable. Penetrations were supplied by Southwest Fabricating and Welding and Tube Turns Co.
These penetrations were ordered to S&L design specification K-1893 and to ASME Section III, 1977 Edition, Winter 1977 Addenda, Class MC.
The following penetrations utilize cooling coils:
Ident.
Line No.
Sleeve Dia.
System IMD-5 1MS01AC24 48" MS IMD-14 1RH09A18 48" RH IMD-9 1CC12AA 50" CC IMD-45 1MS30B3 24" MS There are 22 penetrations in addition to the above which utilize cooling coils of varying heat removal capability.
Baldwin Associates (BA) fabricate in their shops some of the smaller penetrations. These were made to ASME Code Section III, 1974 Edition, Summer 1974 Addenda. Welding records of IMC 53 were examined and this penetration contained diss1milar welds, because the process pipe was stainless steel with a stainless steel closure plate circle and carbon steel sleeve. The process pipe was 10" x 1 3/4" and the closure was 18" in diameter by.375 thick. The stainless steel to stainless steel weld was done using weld procedure NP-8-8-BA-L, Revision 2, while the dissimilar metal weld of the closure circle to sleeve was performed using NP-1-8-BA-L, Revision 2.
Liquid penetrant test on both welds was performed by U.S. Testing Co. using procedure UST-PTC-1 Revision 0.
Qualification of the procedure was performed in the 6G position.
No items of noncompliance or deviations were identified.
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Status Internals Work Installation of CRDM insert and withdraw lines is held up because redesign of the scismic restraints for these lines is underway.
Workers inside the reactor vessel are retensioning the bolts on
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top of the jet pumps.
No items of noncompliance or deviations were identified.
Exit Interview The inspector met with licensee representatives (denoted in Persons Contacted paragraph) on October 29 1981. The inspector summarized the purpose and findings of the inspection, which were acknowledged by the licensee.
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