ML19320B462

Responds to NRC 800505 Ltr Re Violations Noted in IE Insp Repts 50-413/80-05 & 50-414/80-05. Corrective Actions: Individual Cited in Insp Rept Has Met All Requirements for Level 2 & Has Been So Certified

ML19320B462
Person / Time
Site:	Catawba
Issue date:	05/28/1980
From:	Parker W DUKE POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19320B461	List: ML19320B462
References
NUDOCS 8007100419
Download: ML19320B462 (3)

Text

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DUKE POWER COMPANY Powen Ucstonwo

', 422 SouTu Cuencu Starer, CHARLOTTE, N. C. 28242 e

WILLIAM Q. PA R M IC R, J R.

ViC F Pe t t' Df ee' It.t *= 0 6.t; As t A 704 5tta= Pacovetion 3 7 3- 4 : e 3 May 28, 1980 J. P. O'Reilly, Director U.S. Nuclear Regulatory Commission Region II 101 Marietta St., Suite 3100 Atlanta, CA 30303 RE: RII:GFM 50-413/80-05 50-414/80-05

Dear Mr. O'Reilly:

Please find attached a response to Deficiencies 50-413-414/80-05-03, -04 and -05 which were identified in the above referenced IE Inspection Report.

Duke Power Company does not consider any information contained in this inspec-tion report to be proprietary.

Very truly yours, w < sq ,

William O. Parker, Jr.

ROS/mp Attachment cc: Mr. G. F. Maxwell (NRC, Catawba Const.)

8007100419 I

May 28, 1980 R;cpoaro to D;ficiencice Pega Two Catawba Installation Specification CNS-1390.01-00-0095 covering the tagging of safety-related electrical equipment will be issued by June 1, 1980.

Response to Deficiency 50-413-414/80-05-04 Deficiency As required by Criterion V of Appendix B to 10 CFR 50, as implemented by Duke's Topical Report, paragraph 17.1.5, the corporate quality assurance program pro-cedures specify the quantitative and qualitative criteria to assure satisfactory work performance and quality.

Contrary to the above, the procedure for qualification of site inspection personnel does not have provisions for allowing:

(1) Electrical inspection personnel to be visually examined to assute that they can distinguish between the various colors that inspections require.

(2) Level I inspectors to be designated as technical first line supervisors responsible for supervising and directing all of that particular inspec-tion group's daily efforts.

Response

Procedure QA-140; Quality Control Inspector Training was issued on April 14, 1980, to control the training and certification of quality control inspecto's. This pro-cedure. which complements J-1, specifically addresses color perception tests as a prerequisite to certification. Additionally, the revised certification form, QA-140A, contains an entry block for this attribute.

The individual cited in the inspection report has met all requirements for Level II and has been so certified.

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O DUKE POWER COMPANY CATAWBA NUCLEAR STATION Response to Deficiency 50-413-414/80-05-03 Deficiency As required by Criterion XVI of Appendix B to 10 CFR 50, as implemented by Duke's Topical Report, paragraph 17.1.16.2, nonconforming conditions shall be analyzed and appropriate corrective action taken to preclude repetition.

Contrary to the above, appropriate corrective action was not taken for site non-conformance reports numbered 5756 (closed September 5, 1979) and 6104 (closed November 29, 1979); as site drawings are still not being properly identified as nuclear safety related documents, Response  !

In the course of the inspection, the inspector identified two drawings containing Class 1E cables which were not properly idantified as " NUCLEAR SAFETY RELATED." l Subsequent to the inspection a Nonconforming Item Report, Serial No. 8014, was issued and the subject drawings were re-issued on March 27, 1980, properly stamped

" NUCLEAR SAFETY RFLATED."

The inspector also reviewed two additional Nonconforming Item Reports indicating sbmilar problems with two other drawings. As follow up action to prevent the re-currence of this problem in the future, QA Procedure PR-130, Engineering Drawings, and PR-220, Nonconforming Item Reports, will be reviewed with all Design Engineering personnel in the regularly scheduled QA Review training program.

Additionally, Design Engineering has asked the Quality Assurance Department to con-duct a review for the proper identification of engineering drawings. The results of this review will be used to deterLine if further corrective action is necessary.

Response to Deficiency 50-413-414/80-05-05 Deficiency As required by Criterion III of Appendix B to 10 CFR 50, as implemented by Duke's Topical Report, paragraph 17.1.3, design engineering places emphasis on assuring conformance with standards and SAR design commitments.

Contrary to the above, design has failed to translate into drawings or specifica-tions SAR requirements that all Class 1E equipment be distinctively identifiable to their respective safety trains.

Response

In accordance with the Catawba FSAR, Class 1E equipment is identified according to its particular safety train or channel by means of color coded tags. These tags are installed during construction fn recordance with an installation specification.