ML20094E568

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Forwards Rev 0 to TDR 481, SEP Topic VII-1A,Isolation of Reactor Protection Sys from Nonsafety Sys,Including Qualifications of Isolation Devices, Failure Mode & Effects Analysis
ML20094E568
Person / Time
Site: Oyster Creek
Issue date: 08/03/1984
From: Fiedler P
GENERAL PUBLIC UTILITIES CORP.
To: Crutchfield D
Office of Nuclear Reactor Regulation
Shared Package
ML20094E573 List:
References
TASK-07-01.A, TASK-7-1.A, TASK-RR NUDOCS 8408090250
Download: ML20094E568 (2)


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GPU Nuclear Corporation NUhIM7 100 Interpace Parkway Parsippany, New Jersey 07054-1149 (201)263-6500 TELEX 136-432 Wnter's Direct Dial Number:

August 3, 1984 Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Crutchfield:

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 SEP Topic No. VII-1A Isolation of Reactor Protection System From Nonsafety Systems, Including Qualifications of Isolation Devices Code of Federal Regulation (10CFR50.55a(h)) through IEEE Standard 279-1971 requires that safety signals be isolated from nonsafety signals and that no credible failure at the output of an isolation device shall prevent the associated protection system channel from meeting the minimum performance requirements specified in the design bases.

At Oyster Creek Nuclear Generating Station the analog signals from the nuclear flux monitoring system intermediate range monitors (IRMs) and average power range monitors (APRMs) are connected to the plant computer using resistor

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isolation buffer circuitry. There are he isolation devices between the IRMs and APRMs and their process recorders.

During the inte3 rated evaluation of the subject SEP topic, the NRC staff requested GPUN to perform a failure mode and effects analysis (FMEA) to evaluate the need for isolation devices between the nuclear flux monitoring systems and their recorders.

'8408090250 840803 PDR ADOCK 05000219 P

PDR GPU Nuclear Corporation is a subsidiary of General Public Utilities Corporation a

', Dennis M Crutchfield, Chief U.S. Nuclear R:gulatory Commission Page 2 The results of our evaluation indicate that the failure of IRM/APRM process recorders, in any mode, will not compromise the integrity of the Reactor Protection System and therefore, would not create a safety concern.

Therefore, the isolation devices between the IRM/APRMs and their process recorders are not required. Detailed FMEA is provided in the attached report.

Very truly yours, h

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. FTedTeF Vice President and Director Oyster Creek PBF/ dam /0084e Attachment cc: Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 1

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