IR 05000461/1980014
| ML19338E769 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 08/19/1980 |
| From: | Cordero Z, Knop R, Wescott H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19338E765 | List: |
| References | |
| 50-461-80-14, NUDOCS 8010060108 | |
| Download: ML19338E769 (8) | |
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U.S. NUCLFaR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report No. 50-461/80-14 Docket No. 50-461 License No. CPPR-137 Licensee:
Illinois Power Company 500 South 27th Street Decatur, IL 62424 Facility Name: Clinton, Unit 1 Inspection At: Clinton site, Clinton, IL Inspection Condu ed: August 5 - 8, 1980 hY
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Inspectors:
H. M. Wescott
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b Z. C. Cordero
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Approved By:
R. C.
p Projects Section 1 Inspection Summary Inspection on August 6-8, 1980 (Report No. 50-461/80-14)
Areas Inspected: Reactor Pressure Vessel Internals observation of welding activities; follow-up at HQ's request; follow-up of unresolved items; follow-up of noncompliances; follow-up of 50.55(e) reports; fire prevention / protection. The inspection involved a total of 44 inspector-hours onsite by two NRC inspectors.
Results: Of the areas inspected, no apparent items of noncompliance or deviations were identified in six areas. One apparent item of noncom-pliance was identified in one area (Infraction - failure to follow instructions,Section II, paragraph 1).
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DETAILS
Persons Contacted Principal Licensee Employees
- G. M. Brashear, Manager of Clinton Site
- A. J. Budnick, QA Director
- R. J. Canfield, Director of Construction
- L. Dozier, Assistant Director of Construction
- R. Folck, QA
- J. D. Geier, Manager, Generation Engineering
- J. M. King, Assistant Director of Construction
- L. J. Kock, Vice President
- J. O. McHood, Vice President j
M. Tindill, QA Specialist I
Baldwin Associates
- R. D. Bennett, Manager Technical Services
- J. E. Findley, Project Engineer
- W. J. Harrington, Project Manager
- G.
Lane, Electrical QC
- J. Linchan, Manager QC
- J. Smart, Manager QA
- T. Walker, Senior QC Engineer
- C. Winfrey, Senior QC Engineer J. Stone, Manager of Safety General Electric Company
- J. L. Dempster, Site Manager
- S. G. Hall, Quality Control Reactor Controls Incorporated
- C. S. Gaurneir, QC Supervisor Hartford Steam Boiler Insurance Company j
- J. R. Hudson, Authorized Nuclear Inspector
- M. J. King, Authorized Nuclear Inspector
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U.S. Nuclear Regulatory Commission
- H. H. Livermore, Resident Inspector
- Denotes those present at the exit interview.
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Licensee Action on Previously Idnetified Items
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(Closed) Deficiency (461/80-06-07) Annual audit of subcontractor not performed as required by ANSI N45.2.12.
The inspector reviewed IPC's
audit of G.E. performed on June 17 and 18, 1980, dated June 20, 1980, which included the " Pre-Audit Attendance List", " Exit Meeting", and i
" Audit Check List." These appeared to be acceptable.
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(Open) Infraction (461/80-02-04) Excessive NCR's prior to performing corrective action to preclude repetition. The inspector reviewed
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BQA 140, Revision 1, dated December 7, 1978, QA NCR Review w/ Quality Assurance Procedure Change Request QA PCR 22, dated May 19, 1980,
-BQAI 140-1, dated May 8, 1980, NCR Computor Program, Revision 0, and NCR Summary Printout Sheet dated August 6, 1980. The inspector'could
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not determine that corrective action to preclude recurrence had been
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taken as a result of the trend analysis program with the licensee and found that the licensee was also performing his own analysis. Review of the licensee's monthly analysis reports established that an NCR
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count was performed and compared with previous reports, no corrective
action to preclude recurrence was apparent. The inspector could find no correlation between number of NCR's recorded to amount of work completed on a given activity. Example: Number of NCR's per amount of concrete poured per time frame. This item remains open pending corrective action by the licensee.
(Closed) Part 21 Report dated July 3, 1980, twenty-two (22) 2 1/2" x 2" concentric reducers supplied to Clinton site fabricated of J-55 material for use on ASTM A234-WPB. The inspector reviewed a letter from Tube Turns Division to U.S. NRC RIV dated July 3, 1980, stating that the
material had been shipped from the job site but had not been received by Tube Turns. The inspector also reviewed the following:
a.
Baldwin Associates Receiving Inspection Report RIR No. 59873, dated
April 30, 1980, confirming receipt of the 22 reducers.
b.
Certification transmittal, dated April 24, 1980, stating that "The supplier has certified that the material was manufactured to meet ASME SA-234 WPB."
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Detailed Analysis Report by Tube Turns, dated April 15, 1980, (physical and chemical).
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Baldwin Associates, " Items / Materials Returned Report", Report No. 4136, dated June 24,'1980, stating that the 22 reducers were returned to Chicago Tube & Iron Company.
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e.
Chicago Tube & Iron Company, Material Return Authorization, dated June 18, 1980, to Baldwin Associates.
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(0 pen) 50.55(e) Report (Reported on June 25, 1980) Subject: Welding i
deficiency on containment spray piping (RHR) hangers. The inspector determined that the corrective action taken as stated in the final
. report from IPC to the director, USNRC, dated July 28, 1980, (U-0163)
had not been taken. This item remains open pending a follow-up letter from the licensee and verification by the inspector that all work has been accomplished.
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Section I
Prepared by:
H. M. Wescott Reviewed by:
R. C. Knop, Chief Projects Section 1
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1.
Fire Prevention / Protection The Region III inspector accompanied by the Region III resident inspector performed a fire prevention / protection inspection to ascertain whether adequate and approved fire prevention procedures exist to control fire prevention / protection during construction as follows:
The inspector toured three warehouses and inspected twelve type a.
ABC portable fire extinguishers. Four of these were found to be missing the required lead reals.
In addition, one fire exit sign was not illuminated. Immediate action was taken to correct these deficiencies. Fire hose stations appeared to be in satis-factory condition. No evidence of uncontrolled flammable materials was evident. The warehouses are equipped with a sprinkler system.
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b.
The inspector toured the power block and found several portable fire extinguishers with no lead seals and one extinguisher with no locking pin. Fire hose stations were observed to be installed.
As of this inspection, water supplies to permanently installed
fire hose have not been provided.
c.
The inspector toured the pumphouse and observed that a temporary diesel driven fire pump provided with automatic start in the event of loss of water pressure or electrical power. This fire
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pump is to serve as a back-up system when the permanent fire
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pump loops are installed.
Review of security fire equipment check records indicated that i
the temporary fire pump had automatically started one evening for no apparent reason. The security guard placed the diesel in the manual start mode leaving the site without a fire pro-tection water supply for an undetermined length of time. This
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was brought to management's attention at the exit meeting.
d.
The inspector reviewed fire extinguisher inspection records that were performed by the security force end safety department section.
The records indicated that several of the pressure indicator valves (PIV's) were disabled and in need of repair with no indication that
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repairs had been made. This was brought to the attention of the safety department supervisor.
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Storage platforms are provided for gas cylinders and appeared
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te be adegaate. However, No Smoking or Flammabl/ Material signs were not evident in these areas. Gas cylinders in the power. block when not in use were tied off to prevent falling.
f.
Each Baldwin Associates employee is given a pocket size hand-book at the time of employment on general safety requirements including fire safety. These are general in nature.
g.
A fire brigade has been formed made up of supervisory personnel.
Meetings are held periodically to discuss fire safety, and brigade drills have been held according to the safety depart-i ment supervisor. However, no fire drills for office personnel and construction workers have been held. This was brought to management's attention at the exit meeting.
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2.
Fire Loop Installation During this inspection, the two diesel driven fire pumps were in the process of coupling alignment. Therefore, an inspection was not performed. The loop will be inspected at a subsequent inspection.
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e Section II
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Prepared by:
A. C. Cordero Reviewed by:
D. H. Danielson, Chief Engineering Support Section 2 Reactor Vessel Internals - Observation of Welding Activities The inspector observed the field welding of the reactor vessel control rod drive tousing to the bottom head penetration. The following was adhered to and is in compliance with approved licensee procedures.
Weld filler material corresponds with material specified.
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b.
The welding technique for the root and the remainder of the l
joint.
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Starting points of each successive pass are staggered.
d.
Welding procedure used does comply with specifications and j
code requirements.
j Disposition of unused filler materials was in accordance with e.
procedures.
f.
The surface of the finished welds were free from coarse ripples, grooves, overlaps, and appears to meet the specified acceptance i
standards.
The inspector noted a weld rod caddy with coated Inconel 182 filler material that had noc been electrically connected.
Good industry practice requires rod caddies to be electrically connected at all times when in use in the field. The licensee agreca and stated that, indoctrination of welders as
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to the requirements would be done.
The inspector reviewei the Reactor Controls Incorporated (RCI) Process Requirement Sheet for reactor vessel internal installation work. Weld No. 32 for the control rod drive housing weld to the reactor vessel bottom head penetration procedure requires a mock-up weld of the CRD housing to the reactor head using welding procedure Specification (WPS)
43/43 OTS-1, IG/2F position, mock-up no. WMU-32.
Six of the nine welders Performance Qualitication Records (PQR) reviewed indicated the mock-up was done in the IG/1F position. This is an item of noncompliance with 10 CFR 50 Appendix B, Criterion V which requires welding activities to be accomplished according to procedure.
(461/80-14-01)
Except as noted, no items of noncompliance or deviations were identified.
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-Exit Interview The inspectors met with the licensee representativcs (denoted under
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Persons Contacted) at the conclusion of the inspection on August 8, 1980. The inspectors summarized the purpose and findings of the inspection. The licensee acknowledged the findings reported herein, f
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