ML18033B390

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Safety Evaluation of Employee Concerns Subcategory Rept E-C-40500, Matls Identification
ML18033B390
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 05/31/1990
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML18033B375 List:
References
NUDOCS 9006210267
Download: ML18033B390 (2)


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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION EMPLOYEE CONCERNS SUBCATEGORY REPORT E-C - 40500 MATERIALS IDENTIFICATION TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR POWER PLANT DOCKET NOS 50-259 50-260 AND 50-296 I

SUMMARY

OF ISSUES TVA identiffed eighteen concerns fn thfs subcategory.

The eighteen concerns were grouped into fifteen issues to facilitate effective evaluation of similar concerns.

These issues addressed (1) adequacy of marking and storage of ASTM A-307 bolting material; (2) unapproved paint markers used on stainless steel; (3) uncontrolled removal and replacement of valve identification tags; (4) no heat numbers on structural steel; (5) no heat numbers and data on tube steel for hangers; (6)

ERCW buried pipe does not have heat numbers stamped on pipe; (7) inadequate

storage, issuance and traceability of small code items; (8) heat numbers missing or cut off stainless steel pipe; (9) traceability treated differently for ONE/DNC Level I and II materials; (10) requisitions being altered; (11) no heat numbers on HVAC duct supports; (12) heat numbers placed on plates attached to the containment vessel without QA's knowledge; (13) loss of material identification after receipt inspection,'l4) no identification of Q material during storage; and (15) heat number on one end of black pipe is cut off when pipe is cut up.

II EVALUATION TVA has evaluated the 15 issues identified above and concluded that 14 of these issues were not applicable to the Browns Ferry site.

One issue related to loss of material identification after receipt inspection was found to be applfcable to the Browns Ferry site but did not violate any procedures, standards,= or requirements.

For the other TVA's nuclear power plant facflftfes where these issues were determined to be factual, TVA has issued documents to track and resolve the problems.

III CONCLUS IONS.

The-NRC staff concludes that the corrective action taken by TVA to resolve the 15 fssues raised by the 18 concerns included in this Materials Subcategory Report are adequate.

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