ML20153B696
| ML20153B696 | |
| Person / Time | |
|---|---|
| Site: | Vogtle |
| Issue date: | 08/18/1988 |
| From: | Brownlee V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20153B695 | List: |
| References | |
| 50-425-88-19, NUDOCS 8808310054 | |
| Download: ML20153B696 (4) | |
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ENCLOSURE 1 FTICE OF VIOLATION Georgia Power Company Docket No. 50-425 Vogtle Unit 2 License No. CPPR-109 During the Nuclear Re May 11-12, June 6-10, gulatory Commission (NRC) inspection conducted on and July 11-14, 1988, violations of NRC requirements were identified.
The violation involved pipe sup) ort design and construction.
In accordance with the "General Statement of Policy and Procedure for NRC EnforcementActions,"10CFRPart2,AppendixC(1988),theviolationislisted below:
Criterion V of Appendix B to 10 CFR Part 50, ivities affecting quality as implemented by FSAR Chapter 17, Section 17.1.5 states in sart: Act shall be prescribed by documented ins; ructions, procedures, or drawings,
... and shall be accom procedures, or drawings.plished in accordance with these instructions, 1.
Pullman Power Products Procedure X-24, "As-Builting Piping Systems and Related Components", ion necessary for the performance of stress details requirements for as-builting and documentation of informat analysis reconciliation.
Specifically Section 4.1.1, states that "My',ars shall be revised to incorporate the as-built information, when the actual dimension differs from the design dimension beyond applicable measurement tolerance, but is within allowable construc-tion tolerance."
Contrary to the above, the following discrepancies were found to be properly ' redlined' and documented on a copy of the pipe support drawing in the PPP Precess Package, but were not incorporated into the Mylars.
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V2-1204-014-H004, the actual size of item
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o V2-1204-014-H006, the dimension from the centerline W4 to the centerline of the embeded plate, o
V2-1208-005 H007, the dimension for item #4 was shown on the drawing as 3 5/8", the inssectors measured in the field and the
' redline' drawing, both incicated that the dimension was 51/2".
V2-1208-145-H017, the pin-to pin dimension of the spring can, o
drawing shows 12'-10 5/16", and the ' redline' and the dimension i
the inspectors measured was 12'-11".
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Docket No. 50-425 Vogtle Unit 2 License No. CPPR-109
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V2-1208-145-H016 the Bill of Haterials shows item #5 as 8" wide, the inspec, tors measured the dimension as 8 3/4", this is s
the same dimension as the ' redline' drawing, o
Isometric 2X3-1208-146-01, Detail 2 & 3, indicate a class change from 212/FG0 on Line 1208-145-4" to 414/FG4, on Line 1008 A20-1/2",.
The Line Designation List (LDL) shows 1208-A20-1/2" as 424/FG4.
OCN-R #7, dated 2-3-86, changed the line to 414/FG4.
o V2-1208-145-H017, the location of the beam attachment on the drawing shows the 'as-built' dimension as l'-31/2", documen-tation in the Process package and the Final Inspection Report, both show the dimension to be l'-2 3/4".
o Isometric 2X3-1205-006-01, from DCN #8, the class information was not transferred correctly to the isometric.
Also, not all the information from FE0CNR-2262, was transferred to the
'as-built' isometric.
2.
Pullman Power Products, Procedure IX-50, "Pipe Support Fiele
'al-lation and fabrication Procedure", Section 11.1 states in pare aat, "Each support shall be visually inspected for, compliance with the support drawing and this procedure.'
Section 12.5.1, states in part with this procedure.g'that, "The field en ineers will as-built all supports in accord Contrary to the above, the above sections were not met in that, the following drawings, both P&ID and pipe supports were found to have discrepancies between the actual condition in the field and the drawing; or pertinent information was missing from support drawings, V2-1208-055-H052, shows the angle iron, item 5, in the wrong o
orientation, o
V2-1208-055-H014, in the Location Plan the vertical pipe is shown as going in the (-)Y direction, In the field it is going in the (+')Y direction.
o V2-1208-255-H002, the drawing shows the dimension from the centerline of item #2 to the centerline of the pipe as l'-4 1/4" ACT., the inspectors measured l'-2 1/4".
e V2-1204-063-H004, the location of the attachment for V2-1204-201-H002, item #a, to the embed plate, shows the dimension from the right side of the embed plate to the attachment as 2 3/8", tne inspectors ceasured 3 1/16".
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Docket No. 50-425 Wgtie Unit 2 License No. CPPR-109 P&ID 2X408122, )shows a line,(:oordinate-C-5, and just to the le designated as Line 006-8",
o Line 008-8".
o V2-1205-004-H016, in the process package, the "Strut Reconcilia-tion Report" (SRR), of 5-26-87, indicates two struts were installed, SRR of 10-14-86, shows one strut and SRR of 5-18-88,
.l indicates that two struts were installed.
The pipe support drawing, (R/3), shows one strut.
There is also a d screpancy of q
tha offset angles, in SRR of 10-14-86, it indicates 3-degrees, SRR of 5-26-87, indicates 2 degrees.
o V2-1205-006-H014, the Process Package has two different issue tickets for the spring can tL t was 'nstalled, both for the same serial number of 8015060, they also indicate two different spring can sizes, o
V2-1204-063-H007, was installed on the wrong vertical pipe.
The support drawing had the correct location for the support.
3.
Pullman Power Products Procedure IX-50 "Pipe Support Field InstC!ation and Fabrica, tion Procedure", $ection 6.6, states in part that, The locating dimension on the attached support in relation to a connection point on the parent shall be documented on the attached support (baby) drawing."
Contrary to the above, the above section was not met in that, the following pipe support drawings, were found to not have the proper locating dimension of the baby supports.
V2-1208-215-H003, -H004, -H005, all three drawings did not have o
a locating dimension for the attached support (baby) in relation to a connection point on the parent support.
This is a Severity Level V violation (Supplement II.E).
Pursuant to the provisions of 10 CFR 2.201, is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN; Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, within 30 days of the date of the letter transmitting this Notice.
This re)1y should be clearly marked as a "Reply to a Notice of Violation" and shoulc include [for each violation):
(1) tdmission or denial of the violation (2) the reason for the violation if admitted (3) the corrective steps whIch have been taken and the results achieved, (4), the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.
Where good cause is shown, consideration will be given to extending tb response time. If an adequate reply is not received within the
.s Georgia Power Company 4
Docket No. 50-425 Vogtle Unit 2 License No. CPPR-109 time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.
FOR THE NUCLEAR REGULATORY COMISSION V rg Brownlee, Chief Reactor Projects Branch 3 DivisionofReactorProjects Dated at Atlant, Geor thislgdayof 1988 1
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