IR 05000298/1987020
| ML20237J717 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/17/1987 |
| From: | Gilbert L, Ireland R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20237J678 | List: |
| References | |
| 50-298-87-20, NUDOCS 8708260278 | |
| Download: ML20237J717 (4) | |
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i APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection. Report: -50-298/87-20 License: DPR-46 n.
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' Docket:
50-298
. Licensee:. Nebraska Public Power District (NPPD)
P.O. Box 499 Columbus, NE 68601 Facility Name:
Cooper Nuclear Station (CNS)
Inspection At:
Cooper Nuclear Station, Nemaha, NE-Inspection Conducted: July 27-31, 1987 Inspector:
f//2/87 L.' D(Girbert, Reactor Inspector, Engineering Date-Section, Reactor Safety Branch-Approved:
[G NNa, h/ 7k7
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eering Section Date /
R. E. Ireland, T,hief. Engin Reactor Safety Branch (
Inspection Summary
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Inspection Conducted July 27-31, 1987 (Report 50-298/87-20)
Areas Inspected: ' Routine, unannounced inspection of welding and nondestructive examination activities.
I Res'ults: Within the two areas inspected, one violation was identified
.(failure to perform a required examination, paragraph 2).
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8708260270 870820 PDR ADOCK 05000298 G
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DETAILS 1.
Persons Contacted
- G. R. Horn, Division Manager of Nuclear Operations
- E. M. Mace, Engineering Manager
- D. M. Norvell, Maintenance Manager
- J. M. Meacham, Senior Manager, Technical Support
- R. Gibson, Quality Assurance
- C. R. Goings - Merrill, Regulatory Compliance Specialist S. Freborg, Lead Mechanical Engineer
- Denotes attendance at exit interview.
2.
Welding and Nondestructive Examination a.
Review of Procedures The NRC inspector reviewed the following documents associated with welding and nondestructive examination.
- Cooper Nuclear Station Operations Manual, Procedure 0.30, Revision 0, "ASME Section XI Repair / Replacement Program."
Cooper Nuclear Station Operations Manual, Maintenance Procedure 7.7, Revision 14, "NPPD' Welding Specifications for Code Welding."
Cooper Nuclear Station Operations Manual, Maintenance Procedure 7.07, Revision 6 "Special Process Control Maintenance Procedure."
During the review of the welding procedure specifications (WPS) in Maintenance Procedure 7.7, the NRC inspector noted editorial discrepancies concerning revisions to the procedures and technical discrepancies in procedures with materials requiring notch toughness properties.
In the case of the editorial discrepancies, the revision number on the procedure title page was inconsistent with the revision number on the procedure revision history page for the following procedures:
WPS NPPD P1-A, WPS NPPD P1-G, WPS NPPD P8-A, WPS NPPD P8-B and WPS NPPD P1-P8A.
This is considered an open item.
(298/8720-01)
In the case of the technical discrepancies, procedures WPS NPPD P1-B, WPS NPPD P1-F (CVN) and WPS NPPD P1-G contain one or more of the following discrepancies for qualification of notch toughness materials:
(1) the thickness limits of the procedure are not consistent with the requirements of QW-403.6 in ASME Code Section IX for the thickness
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qualified, (2) the materials listed in the procedure as qualified are inconsistent with the requirements of QW 403.5 in ASME Code Section IX for qualification of P-Numbers and Group-Numbers,'(3) the impact test values of the report do not meet the acceptance criteria of ASME Code Section III or the original design specification, and (4) the impact test specimens removed from the welding procedure qualification test assembly were not taken from both the weld metal and heat-affected zone as required by ASME Code Section III and the original design specification. The acceptability of the licensee's use of Procedures WPS NPPD P1-B, WPS NPPD P1-F(CVN), and WPS NPPD P1-G is unresolved pending licensee review of plant records to ascertain if these procedures were used for safety-related welding of materials requiring notch toughness.
(298/8720-02)
b.
Review of Records The NRC inspector reviewed documentation for installation of a replacement valve in the reactor water cleanup piping system.
The documentation reviewed are listed below:
Maintenance Work Request (MWR) #86-4914
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Record #86-651 for weld No. CWA-BJ-8/RWC-3 Record #86-652 for weld No. CWA-BJ-7/RWC-4 Weld Material Requisition 86-3804 Welder Qualification Records Nondestructive Examination Records Hydrostatic Testing Record
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During review of the above documents, the NRC inspector noted that the liquid penetrant examination required by the construction code had not been performed on the two Class 1 welds, CWA-BJ-8/RWC-3 and CWA-BJ-7/RWC-4.
The construction code designated for these welds was ASME Code Section III, 1983 edition including the Summer 1983 addenda.
Article IWA-4000 and Interpretation X1-1-86-51 of ASME Code Section XI requires that, following installation of a replacement component by welding, the required construction code nondestructive examination requirements shall be met in addition to those examinations required for preservice inspection.
Although the welds were liquid penetrant examined for preservice inspection in accordance with ASME Code Section XI,1981 edition including addenda through Winter 1981, the acceptance standards for the preservice examination are less stringent than the construction code.
This is an apparent violation for failure to perform a required examination.
(298/8720-03)
3.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, violations, or deviations.
An unresolved item disclosed during the inspection is discussed in paragraph 2.
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l 4.
Exit Interview The NRC inspector met with the NRC senior resident inspector and licensee
representatives denoted in paragraph 1 on July 31, 1987, and summarized the scope and findings of the inspection.
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