ML19330B868

Responds to IE Bulletin 80-16, Potential Misapplication of Rosemount Inc Model 1151 & 1152 Pressure Transmitters W/ Either a or D Output Codes. Evaluation on 800314 & 28 Showed No Transmitters Could Result in Unambiguous Output

ML19330B868
Person / Time
Site:	FitzPatrick
Issue date:	07/22/1980
From:	Pasternak R POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
IEB-80-16, JAFP-80-591, NUDOCS 8008070105
Download: ML19330B868 (4)

Text

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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITzPATRICK NUCLEAR POWER PLANT RAYMOND J. PAsTERNAK Resident Meneger S P.O. BOX 41 Lycoming,Nm York 13093 315-342 3840 July 22, 1980 SERIAL: JAFP 80-591 Boyce H. Grier, Director United States Nuclear Regulatory Commission Region I 631 Park A" mue King of Prussia, PA. 19406 SUBJECTi NRC BULLETIN 80 POTENTIAL MISAPPLICATION OF ROSEMOUNT INC. MODELS 1151 and 1152 PRESSURE TRANSMITTERS WITH EITHER "A" OR "D" OUTPUT CODES

Dear Mr. Grier:

The FitzPatrick Plant staff has completed its review of the subject Bulletin and the results of that review are presented below in the same order as indicated in the Bulletin.

1) The FitzPatrick Plant uses four (4) Rosemount Model 1151 transmitters in safet code "A" and one (1)model y-related 1152systems which transmitter have using an output output code "A".  !

In additirn, the FitzPatrick Plant plans to install approximately seventy-six (76) additional Rosemount transmitters associated with Analog Trip Transmitter Units during 1981. Some of these transmitters have been received at the plant and have been placed in a " Hold" status by Quality Assurance awaiting resolution of the potential problem described in the Bulletin.

2) The FitzPatrick Plant performed a 10CFR21 evaluation when Rosemount Inc. informed the plant of potential defects on March 14 and March 28, 1980. This evaluation determined that none of the Rosemount transmitters installed at the FitzPatrick Plant could result in an ambiguous output.

8008070/08 Q

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'Boyce H. Grier, Directo- July 22, 1980 '

United States Nuclear Regulatory Comission JAFP 80-591

SUBJECT:

-NRC BULLETIN 80-16 Page '

Tabulated below is additional information for each of the five-(5) transmitters to which the Bulletin is applicable:

, 02-3-PT178C a Complete Mode'l No. 1151GP9A22T0003PB b Transmitter Range Limits 0 to 3000 psig (+ 14 psig static head) c Transmitter Range Setting 14 to 1214 psig d Range of process variable measure for:  :

1) Normal Conditions 0 to 1005 psig  :

2) . Accident Conditions 0 to 1225 psig (FSAR Paragraph 14.5.1.2) e) Values of process variable which could produce anomalous indication None f) Service / Function Reactor Protection System /

High Pressure Trip 02-3-PT1780

, a) Complete Model No. 1151GP9A22T0003PB b) Transmitter Range Limits 0 to 3000 psig (+ 14 psig static head) c) Transmitter Range Setting 14 to 1214 psig l d) Range of process variable l measure for:

1) Normal Conditions

2) Acciderit Conditions 0 to 0 to 1225 1005 psic psig (FSAR Paragraph 14.5.1.2) e) Valua of process variable which could produce anomalous

< indication None ,

f) Service / Function Reactor Protection System /

High Pressure Trip 02-3-PT178A a) Complete Model No. 1151GP9A22T003PB b) Transmitter Range Limits 0 to 3000 psig (+ 14 psig static head) c) - Transmitter Range Setting 14 to 1214 psig d) Range of process variable

^

measure for:

1) Normal Conditions

, 2) Accident Conditions 0 to 1225 0 to 1005psig psig (FSAR Paragraph 14.5.1.2) e). Values of process variable which could produce anomalous indication None

. f) Service / Function Reactor Protection System /

High Pressure Trip m, y .- --- - - . , ,,- - -~,,o- - - - -

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~ Boyce H. Gr_ier, Director July 22, 1980 United States Nuclear Regulatory Commission JAFP 80-591

SUBJECT:

HRC BULLETIN 80-16 Page 02-3-PT178B a) Complete Model No. 1151GP9A22MBGE3 b) Transmitter Range Limits 0 to 3000 psig (+ 14 psig static head) c) Transmitter Range Setting 14 to 1214 psig d) Range of process variable measure for:

1) Normal Conditions

2) Accident Conditions 9 to 0 to 1225 1005 psig psig (FSAR Paragraph 14.5.1.2) e) Values of process variable which could produce anomalous indication None f) Service / Function Reactor Protection System /

High Prassure Trip 23LT201C a) Complete Model No. 1152DP3A22PB b) Transmitter Range Limits 0 to 30 inches water c) Transmitter Range Setting 0 to 12 inches water d) Range of process variable measure for:

1) Normal Conditions 4.5 to 6.0 inches water

2) Accident Conditions 0 to 12.0 inches water - SEE NOTE BELOW e) Values of process variable which could produce anomalous indication None f) Service / Function Level Indication / Pressure Suppression Pool NOTE: Due to the physical arrangement of the Pressure Suppression Pool water level sensing taps, the maximum differential pressure which the transmitter can be subject to is 12.0 inches irregardless of the actual Pressure Suppression Pool level.

3) No corrective action is required for the five (5) transmitters which are currently installed. Corrective action for the transmitters to be installed during 1981 will be completed prior to installation.

The nature of this corrective action is dependent upon additional work by Rosemount and General Electric which has not been completed at this time.

Verytrulyyoyr /

Syp~njkj&wo Ra; "C:brp RAYMOND J. PASTERNAK

Attachment:

Distribution List RESIDENT MANAGER

t ATTACHMENT: DISTRIBUTION LIST NRC BULLETIN 80-16 George T. Berry, PASNY, NY0 G. M. Wilverding, PASNY, NY0 J. P. Bayne, PASNY, NY0 J. F. Davis, PASNY, NY0 M. C. Cosgrove, PASNY, JAF R. Baker, PASNY, JAF H. Keith, PASNY, JAF Document Control Center U. S. Nuclear Regulatory Commission Office of Inspection & Enforcement Division of Reactor Operations Inspection Washington, D.C. 20555 4

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