ML20212N105
| ML20212N105 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 08/26/1986 |
| From: | Partlow J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | White S TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML20212N109 | List: |
| References | |
| NUDOCS 8608280091 | |
| Download: ML20212N105 (4) | |
See also: IR 05000327/1986033
Text
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y p WA3heNf. TON, D. C. 20555 \\*****/ . - AUG 2 61986 Docket Nos. 50-327 . and 50-328 . Tennessee Valley Authority ' - ATTN: hr. S. A. Whi e Manager of NJ: lear Power i 6N 38A Lookout Place i 1101 Market Street Chattanooga, TN 37402-2801 Gentlemen: SUBJECT: REPORT NOS. 50-327/86-33 AND 50'328/86-33 - , The NRC welding team inspection was conducted on June 2-6, June 16-20, and July 7-11, 1986 at the Sequoyah facility. Members of the Office of Inspection and Enforcement (IE), Region II, Office of Nuclear Reactor Regulation (NRR) and a consultant from the Brookhaven National Laboratory (BNL) made up the NRC welding team. This effort consisted primarily of a detailed inspection of selected hardware following TVA's Phase II Report reinspection, a review of . selected portions of the quality assurance program, examination of procedures and records, review of engineering calculations, and a review of the welding documentation history. 1 The NRC welding team noted no significant deviations from the original - construction and licensing requirements in the samples of installed hardware
inspected by the team. Most of the weld deficiencies noted during this , ) inspection were previously identified and evaluated by TVA as a result of its ' reinspection effort. Therefore, the NRC's findings are in general agreement
with the results of TVA Welding Project Phase II Report. However, the NRC ' - welding team identified several deficiencies which warrant additional management attention. The most significant of these deficiencies' involve: (1) the adequacy of drawings to specify which material and quality level of weld requirement apply to the installed hardware; and (2) the cases where the ! actual wild configuration of the hardware did not match the design drawing l requirements. Enclosure 1 identifies items requiring resolution by TVA prior to startup of the plant and is an executive summary of the results of this - inspection and of conclusions reached by the NRC. , The enclosed inspection report details the scope, objectives, and findings and , ! identifies the areas examined during the inspection (Enclosure 2). Region !! will be following your corrective actions for deficiencies identified during i this inspection. Your attention.is invited to the Inspector Followup Items (IFI)identifiedintheinspectionreport. These matters will be pursued during future inspections. '0600280091 060826 . ' PDR ADOCK 0500 7 0 goI g . .
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' . . Tennessee' Valley Authority -2- . In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosures will be placed in the NRC Public Document Rocn. Should you have any questions concerning this inspection, please contact us or the Region II Office. Sincerely, l .24-<.r-, Q ' ' James G. Part ow, Director M Division of Inspection Program: , Officit of Inspection and Enforcement , Enclosures: 1. Executive Summary 2. Insp'ection Report Nos. 50-327/86-33 & 50-328/86-33 cc w/encis: H. L. Abercrombie, Sequoyah Nuclear Plant Site Director P. R. Wallace, Plant Manager D. L. Williams, Jr., Supervisor Licensing Section G. B. Kirk, Compliance Staff Super 91sor , J. E. Wills, Project Manager . - B 0 . , /
. . , , EXECUTIVE' SUMMARY An announced NRC welding team inspection was conducted at the Tennesee Valley i Authority's (TVA) Sequoyah Nuclear Generating Station Units 1 and 2 during the period June 2-6, June 16-20, and July 7-11, 1986. 1 , The NRC welding team reviewed eight open items which were identified by previous NRC inspections; the team was able to close seven of those items. The licensee ! should address and resolve the remaining open item before startup of the
! plant. The team found that TVA had not completed its review of employee concerns , involving welding activities;'therefore, the team could not review this area ' during this inspection. The licensee should complete the review of employee concerns and address those concerns that have been substantiated before startup of the plant. The hardware and documentation that were reviewed for the inspected welding activities were generally in accordance with requirements and licensee , commitments. The NRC welding team noted a number of weld discrepancies which are discussed in detail in Section Ill of the inspection report. Most of these discrepancies were identified and evaluated as a result of the TVA reinspection effort which indicated that the TVA welding project program was effective in
identifying weld deficiencies, however, the welding team did identify additional ! irregularities which in most cases related to the accuracy of welding documentation. These irregularities include: , 1. The guidance was confusing for support inspection requirements provided in drrwings and specifications for instrumentation installations; electrical installations; heating, ventilating and air conditioning installations; j and pipe supports. The team could not clearly identify which supports required Quality Level I inspection and which required Quality Level 2 inspection. Quality Level 1 inspections require documentation for each . weld while Quality Level 2 inspections only require documentation for the ' completed support, l, 2. A number of welds were found to deviate from the requirements of the applicable design drawings. The drawing required one type of weld when, , in fact, the actual weld was found to be some other type of weld, e.g., ! drawings required full-penetration weld while the hardware was installed using flare bevel welds. Section 3 of Volume !! of TVA's revised nuclear performance plan for Sequoyah l provides an action plan that will improve the design control program for the Sequoyah nucicar plant when implemented. This plan includes the reconciliation of "as constructed" and "as designed" drawings to achieve a single set of plant drawings. This plan should address the irregularities identified above to ensure that the welds and welding requirements stated on the "as designed" drawings match the installed hardware, i
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