ML20082A877

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Provides Revised Response to IE Bulletin 80-16, Potential Misapplication of Rosemount,Inc Model 1151 & 1152 Pressure Transmitters W/Either a or D Output Codes. Pressure Transmitters W/A Output Code Used in nonsafety-related Sys
ML20082A877
Person / Time
Site: Oyster Creek
Issue date: 11/09/1983
From: Fiedler P
GENERAL PUBLIC UTILITIES CORP.
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
REF-SSINS-6820 IEB-80-16, NUDOCS 8311180281
Download: ML20082A877 (2)


Text

,O GPU Nuclear Corporation Q

Qf Post Office Box 388 Route 9 South Forked River,New Jarsey 03731-0388 609 971-4000 Writer's Direct Dial Number:

November 9, 1983 Dr. Womas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Dear Dr. Murley:

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 IE Bulletin No. 80-16 This letter revises our reponse, dated July 24, 1980, to the subject bulletin, " Potential Misapplication of Rosemount Inc. Model 1151 and 1152 Pressure Transmitters with either "A" or "D" Output Codes." he Bulletin requested licensees to determine if their facility has installed or plans to install the transmitters in any safety related application. Our original response stated that Oyster Creek did not utilize the subject pressure transmitters in any application:

During a recent NRC Inspection, the inspector and personnel from our engineering department determined that Rosemount pressure transmitters with an output code of "A" are being utilized in a non-safety-related system, the Augmented Off Gas (AOG) building at Oyster Creek. As a result of this determination, a thorough review of our safety related systems was conducted.

W e transmitters in question are not being utilized for any safety related application.

In addition to the concerns of the bulletin, we are expanding our review to non-safety-related systems. Any units found to be in use, such as those in the AOG building, will be evaluated with regard to service application and the ability of the transmitter to perform its intended function.

We original investigation apparently entailed only a cursory review of the non-safety-related systems. W e available documentation does not indicate the depth of investigation regarding non-safety-related applications. With the reorganization of GPU Nuclear, administrative controls were strengthened and the documentation of investigations such as this, is being performed. In order to assure the accuracy and completeness of past responses, a review of 8311180281 831109 PDR ADOCK 05000219 PDR O

GPU Nuclear Corporation is a subsidiary of the General Pubhc Utilities Corporation

Page 2 our documentation packages for those bulletins which the NRC has not yet verified will be condacted on a sample basis. Documentation packages found lacking will be re-investigated.

If you have any questions regarding this item, please contact me or Mr.

Michael Laggart of my staff at (609) 971-4643.

Very truly yours, r7_/ -

p) o Ptier B. Fiedler Vice President and Director Oyster Creek PBF:ML: dam cc: IEC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, IU 08731 j

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