ML19316A256

Forwards Response to 770407 Ltr Re Violations Noted in IE Insp Repts 50-269/77-03,50-270/77-03 & 50-287/77-03. Corrective Actions:Revised All Maint Procedures Re Engineered Safeguard Valves to Include Sign Off Step

ML19316A256
Person / Time
Site:	Oconee
Issue date:	05/02/1977
From:	Parker W DUKE POWER CO.
To:	Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19316A249	List: ML19316A253 ML19316A256
References
NUDOCS 7912050830
Download: ML19316A256 (2)

Text

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( 422 Socra Cauncu Srazzi, CnAar.orre, N. C. asa sa

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4**Cs Petsiegav May 2, 1977 TEtt #=ose E; A* E A 7C4 1 Setae Peocuctio= 373-4083 l

Mr. Norman C. Moseley, Director U. S. Nuclear Regulatory Commission Suite 818 230 Peachtree Street, Northwest Atlanta, Georgia 30303 Re: IE:II:CEA 50-269/77-3 50-270/77-3 50-287/77-3

Dear Mr. Moseley:

With regard to your letter of April 7, 1977, Duke Power Company does not consider information contained in IE Inspection Report 50-269, -270, -287/

77-3 to be proprietary.

Please find attached our response to Items 1.A and 1.B.

7ery ruly yours,

[

w. o. .

William O. Parker, Jr IJB:ge Attachment y912050h3O

/

, RESPONSE TO IE INSPECTION REPORT 50-269, -270, -287/77-3 i

,. ITEM 1A t, T.

l Contra'ry to the requirements of Criterion V of Appendix B to 10CFR50 as implemented by Section 17.2.5 of the DPC QA Topical Report, maintenance performed on January 2,1977, on containment isolation valve 3RC-7 was not in accordance with the approved work request as specified in Section 3.3.2.3 of the Administrative Policy Manual and Station Directive 3.3.5 which resulted in post-maintenance testing not being performed. Unit 1 only.

RESPONSE

This item was previously reported on February 15, 1977 in Reportable Occurrence Report R0-287/77-1. The corrective action identified in this report, which included the review of this incident with appropriate personnel, has been completed. Special emphasis was placed on the necessity of following maintenance procedures properly and the fact that Engineered Safeguards (ES) equipment must be verified operable after maintenance.

In addition, all maintenance procedures dealing with ES valves have been revised to include a sign off step which requires verification of opera-bility after maintenance. This corrective action should eliminate occur-rences of this type in the future.

ITEM 1B

' 'lontrary to the requirements of Technical Specification 6.4.1 , the station was not operated and maintained in accordance with approved radiation con-trol procedures, in that on March 9, 1977, radioactively contaminated trash was found in unlabeled containers and contaminated materials were found outside of a Radiation Control Zone without the required warning tags.

RESPONSE

The failure to use labeled waste containers and the failure to properly label contaminated materials resulted from a coordination inadequacy between the janitorial service and Health Physics when transportation problems developed which prevented the janitorial service from immediately removing the contaminated waste from the area. The waste was properly marked on Maren 9, 1977, and was removed from the Turbine Building basement the morning of March 10, 1977 prior to the NRC inspector's leaving the site.

This item has been reviewed with all personnel in the surveillance unit of Health Physics to assure that they understand how radioactive vaste should be handled under similar circumstances. In addition, the entire Health Physics section is in the process of reviewing all health physics practices and procedures to verify understanding of the procedures and their applicability to the work being done. It is anticipated that this action will prevent future occurrences of this type.

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