IR 05000322/1980007
| ML19320C500 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 05/28/1980 |
| From: | Mcgaughy R, Narrow L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19320C498 | List: |
| References | |
| 50-322-80-07, 50-322-80-7, NUDOCS 8007170288 | |
| Download: ML19320C500 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION Q
OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-322/80-07 Docket No.
50-322 License No.
CPPR-95 Priority Category B
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Licensee:
Long Island Lighting Company 175 East Old Country Road Hicksville, New York 11801 Facility Name: Shoreham Nuclear Power Station, Unit No. 1 Inspection at :
Shoreham, New York Inspection conducted:
April 22-24, 1980 Inspectors:
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L. Narrow, Reat: tor Insp'ector
/ D&te Date Date Approved by:
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RI W. McGa'ughy, g f, Projects Section,
/ Date RC&ES Branch Inspection Sumary:
Inspection on April _22-24,.1980 (Report No. 50-322/80-07)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector of the QC program for certain work in progress, the status of outstanding items and the status of Bulletins and Circulars. The inspection involved 17 inspector-hours on site by one regional based inspector.
Results:
No items of noncompliance were identified.
Region I Form 167 (August 1979)
8007170288
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DETAILS 1.
Persons Contacted Long Island Lighting Company
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B. Cohen, Project Administrator R. DiRoche, QA Specialist W. Doldorf, Superintendent of Construction (Unico)
- W. Hunt, Project Engineer / Construction (Unico)
- J. M. Kelly, Field QA Manager T. Joos, QA Engineer T. Koch, QA Engineer J. McCarthy, Assistant Instrument Supervisor E. J. Nicholas, S6ction Supervisor, Field QA Stone and Webster Engineering (S&W)
- T. T. Arrington, Superintendent Field QC
- J. Carney, Head of SE0
- R. S. Costa, Project QA Manager
- J. Hassett, Senior QC Inspector
- K. A. Howe, General Superintendent C onstruction (Unico)
Courter and Company H. Brittain, NDE Supervisor G. E. Rhedrick, Senior SQAE Engineer M. Tiger, Document Reviewer General Eletric Company
- C. Lukacsy, Control and Instrument Engineer
- Denotes persons in attendance at the exit interview.
The inspector also interviewed other licensee and contractor personnel during the inspection.
2.
Plant Tour The inspector observed work activities in progress, completed work and construction status in several areas.
Work items were examined for obvious defects and for noncompliance with regulatory requirements and licensee commitments.
Evidence of QC activities and quality control of the work was observed.
Specific activities and completed work observed by the inspector included modification of shield plugs for fuel storage pool, the final weld pass of 1 G41*FC4-3-06 FWE, start of work for closing of the opening in the secondary containment wall, the condition of the
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3 equipment hatch which had been brought into the containment building in preparation for its installation, and hydrostatic test of a portion (E-11-37)
of the RHR System.
No items of noncompliance were identified.
3.
Performance of Category I Work by Recor Construction Co. (Recor)
During the plant tour the inspector observed that modification of the fuel storage plugs was in progress and that this work was being performed by Regor.
The inspector was informed that quality control of this work was performed by S&W Field QC in accordance with S&W procedures.
The work in progress was performed in accordance with an S&W E&DCR. The inspector examined E&DCR No. F 19275 which was written for cutting the shield plugs in preparation for fit-up.
Another E&DCR will be written for re-assembly of the plugs.
No items of noncompliance were identified.
4.
Licensee Action on NRC Bulletins The following Bulletins are closed since they were furnished for informa-tion purposes only and had been forwarded to appropriate personnel.
(Bulletin 79-05 and Supplements):
Nuclear Incident of Three Mile
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Island (Bulletin 79-06 and Supplements):
Review of Operational Errors
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and System Misalignments Identified During the Three Mile Island Incident (Bulletin 79-13 and Revisions):
Cracking in Feedwater System Piping
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(Bulletin 78-12 and Supplements):
Atypical Weld Material in Reactor Pres-sure Vessel Welds.
This item is closed based on submittal of a report on this subject to the Division of Reactor Construction Inspection by the RPV Manufacturer, Combustion Engineering (CE) and a certification by CE stating that the above report addresses all of the material used in fabrication of the Shoreham RPV.
Vital Area Access Controls.
This subject has been addressed in the Physical Security Plan for the Shoreham plant and will be evaluated during review of this plan.
5.
Licensee Action on NRC Circulars i
The circulars listed below are closed based on information available on site from S&W and General Electric Company to the effect that the equipment identified in the circulars has not been used on the Shoreham site.
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(Circular 78-15):
Tilting Disc Check Valves Fail to Close With
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Gravity in Vertical Position (Circular 79-19):
Loose Locking Devices on Ingersoll Rand Pumps
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(Circular 79-20):
Failure of GTE Sylvania Relay, Type PM Bulletin
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7305, Catalog SU12-11-AC With A 120v AC Coil 6.
Review of Nonroutine Events Reported by the Licensee The licensee had reported a significant deficiency in accordance with 10 CFR 50.55(e) by letter dated June 29, 1979.
The deficiency consisted of lack of penetration of the root pass for attachment welds of lugs to class 1 piping.
The licensee initially identified three field and two shop welds as nonconforming.
Further investigation by the licensee revealed that all 142 class I lugs showed some lack of penetration.
In addition, material test records for 100 of the lugs were incomplete.
The inspector examined NR No. 88 which identified the nonconformance of the original five lugs and was disposition by reference to E&DCR F-21377 and supplements A through E.
These EDCR's required UT examination of all lugs, provided for repair or replacement of all lugs and NDE following repair or replacement.
The inspector examined selected inspection reports and documentation showing material control of the replacement lugs.
The inspector had no further questions concerning this item.
7.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on April 24, 1980.
In addition, the NRC Resident Inspector, Mr. J. C. Higgins attended the meeting.
The inspector summarized the scope and findings of the inspection.
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