IR 05000416/1979009
| ML19242A509 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/18/1979 |
| From: | Herdt A, Rausch J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19242A505 | List: |
| References | |
| 50-416-79-09, 50-416-79-9, 50-417-79-09, 50-417-79-9, NUDOCS 7908020544 | |
| Download: ML19242A509 (5) | |
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Report Nos. 50-416/79-09 and 50 '.17/79-09 Licensee: Mississippi Power and Light Company P. O. Box 1640 Jackson, Mississippi 39205 Facility Name:
Grand Gulf Units 1 and 2 Docket Nos. 50-416 and 50-417 License Nos. CPPR-118 and CPPR-119 Inspection at Gr GuJf Nuclear Power Plant near Port Gibson, Mississippi I' / 7 ' 7/
m-Inspector u Date Signed
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Approv-bf A. R. Herdt, Section Chief, RCES Branch date Signed SUMMARY Inspection on May 2-4, 1979 Areas Inspected Thi s routine, unannounced inspection involved 19 inspector-hours on site in the implementation; licensee f ollowup of 50.55(e) and Part 21 areas of QA program items, electrical cable clamps, control of weld filler material, weld procedure circuit separation, and solder joints; and inspe tion of construction revision, activities in progress.
Results No apparent items of noncomplaince or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees T. E. Reaves, Manager of Quality Assurance
- P. C. Sly, Quality Assurance Field Supervisor
- J. C. Fuller, Quality Assurance Representative A. T. Famey, Quality Assurance Representative Other licent e employees contacted included construction craftsman, techni-cians, and office personnel.
Other Organizations R. L. Scott, Bechtel Qaulity Assurance Manager
- J. W. Yelverton, Bechtel Quality Assurance Engineer J. L. Martin, Bechtel Quality Assurance Engineer P. S. Collins, Bechtel Quality Assurance Engineer
- A. S. Bettencourt, Bechtel Quality Assurance Engineer
- Attended exit inte rview.
2.
Exit Interview The inspection scope and findings were summarized on May 4, 1979, with those persons indicated in Paragraph I above.
Discussion included Q/,
program implementation, status of unresolved items, 50.55(e) items, Part 21 items, structural steel supports for the Unit 1 RHR heat exchanger, QC records and installation. Status of project was discussed.
Licensee Action on Previous Inspection Findin: 3 (Open) Deviation 416/79-02-01 Failure to control weld filler material The uncontrolled electrode problem was addressed by Bechtel QA through issuance of a Quality Actico Request (QAR-F-097). The QAR required determi-nation of cause and corrective action to prevent recurrence.
The final report was submitted by Bechtel to MP&L who in turn provided the NRC with a written reply dated April 23, 1979. This item will remain open pending an evaluation of the written response and a subsequent inspection by an NRC inspector.
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Unresolved Items 4'J 0l0 Unresolved items were not identified di ring this inspectio.
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Licensee Identified Items (0 pen) 50-55(e) item (416/417/79-09-01), Ttbe Turns fittings f abricated a.
from material with excessive carbci content. MP&L reperted on April 18, 1979, that the following 4" stann., d long radius 90 elbows, SA234WPB, manufactured by Tube Turns had been received and are suspected to have a carbon content beyond the range allowed:
12 pcs., Liberty Equipment & Supply Co.
80 pcs., Consolidat ed Pipe & Supply 11 pcs.*, Texas Pipe Bending
- Fabricated into pipe spools.
A Part 21 report was submitted to the NRC:IE on April 4, 1( '9 and April 12, 1979 by Liberty Equipment & Supply Co.
and by Tuce Turns respectively.
During this inspection the NRC inspector de te rmined that the licensee has taken the following action to track this item:
(1)
Issued a Management Corrective Action Report No. 49 to determine the extent of the problem and to preclude recurrence.
This action includes determing the total number of parts received f rom ell sources identified as beat ho. W6719 (2)
Issued Nonconf ormance Reports #3507 and 3542 to identify the and to location of all parts received, identify those discrepant provide the information to project engineering. These NCRs will also serve to forward information to the Project Quality Assurance Manager for anelysis and verification.
This item will rema?n a final report from the licensee.
No items of open pending noncompliance or deviations were identified.
b.
(Open) 50.55(e) Item 416/417-79-06-01 Improper Ctreuit Separatten in PGCC.
The subject item, reported by MP&L under terms of 50.55(e) on March 23, 1979, has not yet been resolved. GE and HP&L disagree on the accetabi-lity of circuit separation in the G.E. supplied Power Generation Control Complex (PGCC).
MP&L has submitted an interim report to the NBC which promises a final report by June 29, 1979.
(0 pen) 50.55(e) Item 416/417/79-06-02 Inadequate Solder Joints on the c.
480V Load Center.
Tl licensee has replied to the subject item with a written response da ed April 23, 1979. The licensee response is an interim report with a final response targeted for June 15, 1979.
The licensee's AE ha s from Gould I&E, the supplier of the 480V not yet received the report load center that contained the def ective static trip units.
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Inspector Followup Items (Open) IFI item 416/417/78-15-07, Atypical Vessel Weld Material In a.
Peactor Pressute Vessel Welds,Bulletin 78-12,78-134,and 78-12B. The licensee had been advised earlier by NRC Region II that requests received for extending the response deadline beyond May, 29, 1979, would not be granted. In addition the licenseewas advis2d that enf orce-ment action may have to be considered if the buyers and sellers do not provide the information requested in the bulletin. During this inspec-tion the NRC inspector examined the licensee's action and followup to assure a timely response to the subject bulletin. The licensee advised that they were inf ormed that the generic reports were to have been submitted by the reactor vessel manufacturer to the NRC on May 1, 1979.
In addition, information not in the generic report but requested by the bulletin has been promised by the reactor vessel manufacturer to MP&L by May 20, 1979.
b.
(Open) IFI item 416/79-02-02 Defect Removal. The licensee has requested a code interpretation concerning this item by May 18, 1979. This it m will remain open pending this response and Bechtel's action on the matter.
c.
(0 pen) IFI item 416/417/78-23-01 Weld Procedure PI-AT-LH-CVN, Interpass Temperative Specified by ASMI Code Not Included in Procedure.
Bechtel has reviewed this item and has provided a response to MP&L via CAR 217 on March 30, 1979. Resolvement of this item is pending MP&L's acceptance of the Bechtel Solution.
The NRC inspector will examine the solution for acceptance when it becomes finalized.
d.
(Open) IFI 416/79-01-01 Cables Clamps in Control Room. NCR 3296 has been issued to note the nonconforming condition with strain relief clamps.
GE has been requested to inspect, verif3 and provide the resolution CE has issued a Field Deviation Instruction No. WAGN MP&L expects a reponse f rom G.E. by July 1979.
e (Open) IFI 416/78-15-06 Failure to Include All Non-essential Variables in Welding Procedure. MP&L's Discrepancy and Corrective Report (D&CR)
No. 1097 which identified the problem has been closed and the problee tracking transferred to MP&L's Corrective Action Requests (CAR's) No.
216 and 217. Bechtel has responded to MP&L on March 30 and April 18, 1979 as required. MP&L has not yet accepted the solutions recommended by Bechtel 7.
Independent Inspection The inspector examined most areas of Units 1 and 2 to observe construction work and related activities in progress, to inspect the general state of cleanliness, and to examine inplace conditions of mechnical and electrical ne3 4 -
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equipment. The inspector went through the reactor buildings and auxiliary buildings to observe the general condition and protection of piping sub-assemblies, cable trays, pumps and other satety related equipment.
No items of noncompliance or deviations were identified.
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