IR 05000416/1981058
| ML20040C448 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/30/1981 |
| From: | Ang W, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20040C444 | List: |
| References | |
| 50-416-81-58, IEB-79-14, NUDOCS 8201270656 | |
| Download: ML20040C448 (5) | |
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8 NUCLEAR REGULATORY COMMISSION g
I REGION 11 c
101 MARIETTA ST., N.W.. SulTE 3100 o
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ATLANTA, GEORGIA 30303
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Report No. 50-416/81-58 Licensee: Mississippi Power and Light Company P. O. Box 1640 Jackson, MS 39205 Facility'Name: Grand Gulf Docket No. 50-416
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License No. CPPR-118 Inspection at Grand Gulf Nuclear Station near Port Gibson, Mississippi Inspector: ;!$
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Date Signed
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'A. R.' HErdt, Settion Chief D(te Signed
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Engir.eering Inspection Branch
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Engineering and Technical Inspection Division SUMMARY Inspection on December 8-11, 1981 I
Areas Inspected This routine, unannounced inspection involved 26 inspector-hours on site in the i
l areas of seismic analysis for as-built safety related piping systems (IEB 79-14).
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Results l
l Of the areas inspected, no violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- G. B. Rogers, Jr., Site Manager J. W. Yelverton, QA Field Supervisor
- J. S. Cash, Project Engineer
- D. F. Mahoney, QA Representative
- D. D. Little, QA Representative
- R. A. Ambrosino, Nuclear Support Manager Other Organizations Reactor Controls Incorporated D. G. Brock, Site Manager Bechtel Power Corporation
- J. D. Heaton, Project Quality Assurance Manager
- R. Trickovic, Project Engineer
- L. Lushbaugh, Lead Stress Engineer NRC Resident Inspector A. Wagner
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on December 11, 1981 with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection findings. No dis-senting comments were received from the licensee. IFI 81-37-01, " Clearance and Interference Inspection Discrepancies" and IFI 81-37-02, "Zero Gap for Pipe Support / Restraints" were closed - see paragraph 5.
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items were not identified during this inspection.
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5.
Seismic Analysis for As-Built Safety Related Piping Systems (IEB 79-14)
A follow-up inspection to the inspection documented in NRC/RII Report Number 50-416/81-37 was performed to verify licensee compliance with IEB 79-14 requirements and licensee commitments. During the inspection a preliminary copy of the licensee's revised bulletin response, letter AECM-81/474 was reviewed and discussed with the licensee.
Inspector Follow-up Item 416/81-37-01 noted clearance and interference inspection discrepancies.
The licensee subsequently required reinspection of safety related piping systems during the IEB 79-14 walkdowns and during engineering review team's final room and area walkdowns. The inspector has no further questions on this item. This item is closed.
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Inspector Follow-up Item 416/81-37-02 noted that Bechtel Specification 9645-MS-16 allowed zero gap between supports / restraints and piping with operating temperatures that are less than 150 F.
The licensee's A/E per-formed a study (AECM-81/474) to justify the specification. The inspector has no further questions on this item. The item is closed.
The IEB 79-14 sampling walkdown of seven systems was approximately 90 percent complete.
System B21, Main Steam and Feedwater System, was ran-domly selected by the NRC inspector and partially inspected. A review of the walkdown records confirmed compliance with IEB 79-14 requirements and showed attention to details by the walkdown teams in general. The follow-ing system B21 pipe supports / restraints were inspected:
Q1821G021R02 N1821G0021R03
N1821G0021H21 N1821G0021C06 N1821G0021C05
NIB 21G0021R04 Support / Restraint Q1821G021R02 was a safety related, seismically analyzed support / restraint. The NRC inspector noted that a vertical member, Piece 1, had been installed on the east side of the support in lieu of the drawing
required west side. This also resulted in a shorter weld for the member.
These conditions had not been noted by the IO 79-14 walkdown team. Subse-quent investigation by the licensee revealed that QC had previously identi-fied the condition and FCR PS-378 had been prepared for design evaluation
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and resolution but the walkdown team had not been aware of the FCR.
l Support / restraint N1821G0021H21 was a non-safety-related support / restraint.
However it was part of a piping seismic analysis and would affect.the i
analysis. The distance from its baseplate to the centerline of its strut was observed to be 12" in lieu of the drawing required 10".
Bechtel Speci-
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fication MS-16 allowed a tolerance of 3" for non-safety-related, non-seis-j
mically analyzed support / restraint dimensions, and 1" for safety-related, seismically analyzed support / restraint dimensions. This condition had not
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been identified by the IEB 79-14 walkdown team.
Support / restraint NIB 21G0021C05 was within one inch from the support for valve F147A. This condition had not been identified by the IEB 79-14 walkdown team.
The Bechtel Stress Group Leader however, stated that the relative movements were away from each other and that it did not appear to be a problem. This was partially confirmed by the support / restraint drawing. The conditions noted on three of the six supports / restraints inspected diminished the accuracy of the implementation of. the IEB 79-14 walidowns by the walkdown team. The licensee's A/E agreed to evaluate this condition and determine its implica-tions on the IEB 79-14 walkdown program and to resolve the condition. This item shall be identified as Inspector Followup Item 81-58-01 "IEB 79-14 Walkdown Discrepancies".
Reactor Controls Incorporated (RCI) was responsible for designing, fab-ricating and installing Control Rod Drive System piping and supports / -
restraints.
Approximately 30 percent of their fabrication / installation was complete and approximately 10 percent had been inspected. An inspec-tion of the partially completed work and preliminary inspection records was performed to deterMne compliance with IEB 79-14 requirements. The inspection revealed that QC did not record drawing revisions.
It was further noted that partial inspections were being informally tracked by the QC supervisor. The drawings being used for inspections in some cases were telecopy reproductions which were not entirely legible. The RCI site manager agreed to correct the above noted conditions.
The above noted piping system will be further inspected during subsequent IEB 79-14 inspections.
This item shall be identified as Inspector Followup Item 81-58-02 "RCI Piping and Pipe Support Inspections".
Item 4.0 of IEB 74-14 requires that if non-conformances are found, the licensee should describe measures which are in effect that provide assurance that future modifications of piping systems, including their supports, will be reflected in a timely manner in design documents and the seismic analy-sis. The following procedures were reviewed:
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Nuclear Plant Engineering Administrative Procedure 01-304, Revision 1, j
Performance of Design and Preparation of Design Change Packages.
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Nuclear Plant Engineering Administrative Procedure 01-305, Revision 1,
-Preparation and Control of Engineering Calculations / Analysis l-c)
Station Administrative Procedure 01-S-07-01, Revision '4, Control of
Work on Plant Equipment and Facilities
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Station Administrative Procedure 01-S-07-4, Revision 3, Plant Changes and Modifications.
l Although the procedures noted above generally provided controls for plant changes and modifications, controls for piping, pipe supports and their'
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applicable seismic / hanger analysis were not specifically noted.
The licensee agreed to review the noted condition and to provide a resolutitm.
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This item shall be identified as Inspector Followup Item 81-58-03 " Controls for Pipe Support Changes and Modifications".
Pending licensee completion of IEB 79-14 Requirements and commitments, the bulletin shall remain open. No violations or deviations were identified.
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