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x jersey Central Power & Light Company MADISON AVENUE AT PUNCH BOWL ROAD
- MORRISTOWN, N.J.07960
- 201-539-6111 mauene or rus y
Public Utilities Corporation General srsrs =
January 27, 1976 Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region 1 United States Nuclear riegulatory Commission 631 Park Avenue
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King of Prussia, Pa.19406
Dear Mr. O'Reilly:
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Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219
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I6E Inspection Report No. 50-219/75-26 This is in reply to your letter of December 31, 1975 to Mr. I. R.
Finfrock, Jr., regarding the inspection conducted by Mr. E. Greenman on November 17-21, 1975 at our Oyster Creek Nuclear Generating Station.
In regard to Item A of Appendix A,which involves the drilling of two penetrations adjacent to the reactor control room into the cable spreading room, we wish to comment as follows:
Plant Procedure No.105, " Maintenance, Repair, and Modification Control", and Oyster Creek Quality Assurance Procedure No.,2006, "Modifi-cation, Non-Routine Maintenance and Repair" are both tied to the Quality Assurance Systems List (QASL). The cable spreading room does not appear
'on this list. Also, by the same list restrictions on cable penetrations apply only to the primary and secondary containment systems.
It is our opinion, therefore, that a design review, a written safety evaluation, nor a formalized work authorization were required for the work project of concern. However, recognizing that the cable spreading room contains cables of many safety-related systems, we believe that this reom, including penetrations, should be placed on the QASL.
The necessary steps will be taken to have this done.
i In response to Item B of Appendix A, which involved violations of Technical Specification 6.2. A.1 and 6.2.c and Operating Procedure No.
304, we wish to notify you of the following-1
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9604220077 960213 PDR FOIA DEKOK95-258 PDR
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Mr. : James P. 0' Reilly Page-2 January 27, 1976 Operations personnel will be advised via a memorandum of the details of_ the event, the critical importance of system valve lineup checks, and the importance of immediately reporting instances in which valves are found to be incorrectly positioned. The review of this memorandum by Operations personnel should be completed by February 14, 1976.
In response to Item C of Appendix A, which involved violations of our commitment to ANSI N45.2.3-1973, Section 3.2.3, " Fire Protection and Prevention",
please be advised of the following:
Instructior.s. which address fire prevention measures regarding combustible materia
- s during welding or other processes which may involve ignition sources, have been drafted and will be formalized in an overall administration procedure. These instructions include requirements f6f^ fire preventive equipment and precautions to be employed to provide protection for combustible material.
Review and approval of the procedure is expected to be completed by March 15, 1976.
It should be noted that fire prevention con-siderations are being included, as applicable, in each of the various maintenance procedures utilized at the station and that the need for sound fire prevention practices has been stressed at recent plant-wide safety meetings with station personnel and with contractor supervisory personnel who are directing various maintenance. activities.
Very truly yours,
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Donald A. Ross, Manager i
Nuclear Generating Stations pk t
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