ML20217B320

Notice of Violation from Insp on 901203-1214.Violations Noted:Util Did Not Record Interpretation of Porosity in Radiographic View 2-3 of Weld in Field Replacement of Rcrs Piping in Unit 1

ML20217B320
Person / Time
Site:	Brunswick
Issue date:	02/21/1991
From:	Gibson A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20217B251	List: IR 05000324/1990048 ML20217B244 ML20217B320
References
50-324-90-48, 50-325-90-48, NUDOCS 9103120057
Download: ML20217B320 (2)

Text

--

p-- 1

.. . I NOTICE OF VIOLATION Carolina Power and Light Docket No. 50 325 Brtmswick Steam Electric Power Station License No. DPR 71 During an NRC inspection conducted in the period December 3 through December 14, 1990, three violations of the NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR 2, Appendix C (1990), the violations are set forth below:

A. 10 CFR 50.55a (c)(1) requires that components which are a part of the reactor coolant pressure boundary meet the requirements for Class I components in Section ill of the ASME Boiler and Pressure Vessel Code. The Carolina Power and Light (CP&L) specification (248-158 Revision 1) for neld replacement of Reactor Coolant Recirculation System (RCRS) piping in Unit 1 of the Brunswick Steam Electric Power Station (BSEP) requires Nondestructive Evaluations (NDE) be performed in compliance with the requirements of the ASME Boiler and Pressure Vessel Code Sections III and V (1986 Edition without Addenda). Paragraph T-292 of Section V,

' Article 2, requires the interpretation of each radiograph be recorded on a review form accompanying the radiographs.

Contrary to the above requirements, CP&L did not record, on report AFR2-8, the interpretation of porosity in radiographic view 2-3 of weld IB32FFA-12-FWRRB10A in the field replacement of RCRS piping .in Unit I at BSEP.

This is a Severity Level IV violation.

B. 10 CFR 50, Appendix B, Criterion V, requires activities affecting quality be prescribed by documented procedures, and the activities accomplished in accordance with the procedures. CP&L's documer..ed procedure for the Ultrasonic Evaluation of piping systems, in compliance with the requirements of the ASME Boiler and Pressure Vessel Code Section XI, paragraph IWB-3514.3 (1980 Edition with the Winter '81 Addenda) NDEP-425, Revision 0 with Interim Change 1, requires the recording of suspected Daws and indications of geometric or metallurgical origin.

Contrary to these requirements, CP&L did not record suspected flaws in the form of lack of fusion which were disclosed by an NRC independent ultrasonic evaluation and indications of geometric origin which were also disclosed by an NRC independent ultrasonic evaluation contained in weld 1-G31-1095 in the Reactor Water Clean-up -

System (RWCS).

This is a Severity Level IV violation.

9103120057 910226 PDR ADOCK 05000324 0 PDR

Notice Of Violation 2 C. 10 CFR 50.55 (g)(3) requires that components classified as ASME Code Class 1,2 or 3 meet the presenice examination requirements set forth in Section XI of the ASME Boiler and Pressure Vessel Code. Examinations performed by CP&L under this rt.quirement are to the 1980 Edition (with '81 Addenda). The requirement under Appendix III in Section XI, paragraph 3500, part (i), requires the recording of special transducer wedges in the calibration documentation for ultrasonic examinations.

Contrary to this requirement, the documentation of calibration for the preservice ultrasonic examination of weld IE218-39-FW6 did not record the use of a specially altered transducer wedge, when this special wedge was critical to obtaining the volumetric coverage recorded in the inspection report.

This is a Severity Level V violation.

Pursuant to the provisions of 10 CFR 2.201, Caralina Power and Light is hereby required to submit a written statement or explanation to the li. S. Nuclear Regulatory Commission, ATFN: Document Control Desk, Washington, D.C. 20555, with a copy to the NRC Resident Inspector, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a " Reply to a Notice of Violation" an.

should include for each violation: (1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. If an adequate reply is not received within the time specified in the Notice, an order may be issued to show cause why the license should not be modified, suspended or revoked, or why such action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.

.WI .- '/ t Albert F. Gibson, Director Division of Reactor Safety Dated at Atlanta, Georgia this 21st day of February 1991 l

. - - . - - - - - - - - - - - - - -