ML20141E436

Final Significant Const Deficiency Rept Re Failure of Electrical Amplifier Assembly in Tobar Transmitters to Function During Irradiation Testing.Initially Reported on 860303.Seven Transmitters Will Be Replaced

ML20141E436
Person / Time
Site:	Hope Creek
Issue date:	04/01/1986
From:	Corbin McNeil Public Service Enterprise Group
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8604210464
Download: ML20141E436 (3)

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Pubhc Service Electric and Gas Company Corbin A. McNeill, Jr. Pubhc Serwce Electric and Gas Company P.O. Box 236. Hancocks Bridge, NJ 08038 609 339-4800 Vice President-Nuclear April 1, 1986 Dr. Thomas E. Murley, Administrator U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Dr. Murley:

SIGNIFICANT CONSTRUCTION DEFICIENCY ENVIRONMENTAL QUALIFICATION OF TOBAR TRANSMITTERS HOPE CREEK GENERATING STATION On March 3, 1986, a verbal report was made to Region I, Office of Inspection and Enforcement representative, Mr. J. Strosnider, advising of a potentially significant construction deficiency concerning environmental qualification of Tobar pressure trans-mitter polyester housing and base assemblies. The following final report is provided.in accordance with 10CFR50.55(e).

Description of the Deficiency Fifty-three (53) Tobar Model 32 Series 2 transmitters included in the harsh Environmental Qualification Program were found to be supplied with polyester housing and base assemblies which were not environmentally qualified. A program was immediately initiated to qualify the polyester housing and base assemblies to the environmental requirements. During this test program, the electrical amplifier assembly of the transmitters failed to function during irradiation testing.

Safety Analysis

! The Tobar pressure transmitters are installed in various safety

. related systems including High Pressure Coolant Injection (HPCI),

l Residual Heat Removal (RHR), Station Service Water, and Reactor l Core Isolation Cooling (RCIC). The transmitters are intended

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Dr. T. E. Murley 2 4-1-86 j to provide control and initiation signals, and process infor-mation to the operator during emergency modes of operation.

! Failure of the transmitters during accident conditions could

[. result in transmission of false signals to the operator or loss of control / initiation signals which could, in turn, 1 adversely affect safe operation of the plant. We therefore i conclude that the subject deficiency is reportable in accordance with 10CFR50.55(e).  ;

Corrective Action i

. As a result, the fifty-three Tobar Model 32 Series 2 transmitters which, although could not be qualified for harsh environmental  !

conditions, are qualified for mild environments, will be i replaced with Rosemount Model ll53B transmitters which are qualified for-harsh environmental conditions. The qualifi-

! cation of these Tobar and Rosenount transmitters is documented

-in the HCGS Environmental Qualification Summary Report.

I Seven (7) of the Tobar transmitters will be replaced with Rosemount ll53B transmitters prior to fuel load. These seven transmitters are components within the Safety Auxil-I iaries Cooling System (SACS) and the Residual Heat Removal System (RHR). Six transmitters in the SACS are being replaced  ;

to support normal operation of this system which will be required at fuel load, and the seventh transmitter, in the RHR system, was originally planned to be replaced at the time

i. the test plan was developed for the polyester housing / base assembly qualification. The balance, or forty-six (46) of the polyester style Tobar transmitters, will be replaced with Rosemount ll53B transmitters prior to initial criticality.

All fifty-three transmitters being replaced are located in areas outside primary containment, but inside the Reactor Building.

i The environmental conditions in these areas are not capable of i becoming harsh until after initial criticality is achieved.

. Therefore, these transmitters will only experience mild environments prior to initial criticality. j

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Dr. T. E. Murley 3 4-1-86 We have notified the Director of Nuclear Reactor Regulation, by letter dated March 26, 1986, of our plans and submitted the necessary information identifying the Reactor Building as a non-harsh environment prior to initial criticality.

Sincerely, Ng C Office of Inspection and Enforcement Division of Reactor Construction Inspection Washington, D. C. 20555 NRC Resident Inspector P. O. Box 241 Hancocks Bridge, NJ 08038 Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, GA 30339