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-4 Jersey Central Power & Light Compan9 9
k MADISON AVENUE AT PUNCH BOWL ROAD e MORRISTOWN, N.J.07360
- 201539-6111 m u uu r u,,,s g, "))", pubne uunnes corporanon cenerai um, 1
May 27, 1975 i
Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region i United States Nuclear Regulatory Commission 631 Park Avenue
' King of Prussia, Pennsylvania 19406
Dear Mr. O'Reilly:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Status "eport for IE Bulletins No. 75-04 and No.75-04A In my response of April 24, 1975 to IE Bulletins No. 75-04 and No.75-04A, some of the actions described for fire prevention and suppression at the Oyster Creek Nuclear Generating Station were in progress. This letter provides a status of these activities as requested in the Bulletins.
The " procedure preparation guidelines" that specifically incorporate parts "a" through "c" of Item 3 of Bulletin No.75-04A have been completed.
Realize that such a " guideline" is dynamic and will continuously be improved and expanded through operating experience.
The Generation Engineering Department of Jersey Central Power G Light Company has undertaken a project to install an additional fire protection system in the Cable Spreading, Battery, and 460-volt Switchgear Rooms. The system will be a Halon 1301 " Total Flooding" system.
Currently, fire detection devices and flame retardent materials for use in the system are being investigated.
The project's estimated completion date is December, 1975. Monthly status reports will be forwarded to you until the project is completed.
Initial laboratory flammability tests for the various seal materials used at tho Oyster Creek Nucicar Generating Station in cicetrical penetrations from the Reactor Building into the 460-volt Switchgear Room and from the Cable Spreading Room into the Control Room have been completed. The tests were a g
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Mr. O'Reilly May 27,' 1975 modification of ASTM Standard D635, and consisted of touching the end of the blue kernel of a bunsen burner flame to the test material (placed on an asbestos board) for 30 seconds, withdrawing it, and measuring the time to self-extinguish-ment. The results were:
Kaowool - Self-extinguished in less than 1 second.
Glass Fibers - Self-extinguished immediately; some melting at point of flame contact.
Isofoam - Sample consumed 90 seconds after flame withdrawn; material.
sputtered releasirig sparks during flame contact and after flame was withdrawn.
Isofoam is only used on the outside of Reactor Building cabic tray penetrations. That is, the isofoam does not extend from one side of the seal to another (i.e., it is only 1 inch to 2 inches thick).
The emergency Shutdown Procedure modification to specify the sequence of alternative cooling mechanisms has not been accomplished yet, and the emergency procedures revision (to reflect new formats consistent with applicabic guides and standards) and Plant Operations Review Committee review has not been completed. The status of these modifications and reviews will be reported to you next month (i.e., prior to July 1,1975).
Very truly yours, Yazald Os7W, 0
Donald A. Ross, Manager Generating Stations-Nuclear Cs I
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