ML19344A896
| ML19344A896 | |
| Person / Time | |
|---|---|
| Issue date: | 06/27/1980 |
| From: | Pappas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wright G ILLINOIS, STATE OF |
| References | |
| NUDOCS 8008220489 | |
| Download: ML19344A896 (2) | |
Text
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[/C p ucg#'o UNITED STATES F
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NUCLEAR REGULATORY COMMISSION REGION lli
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GLEN ELLYN, ILLINOIS 60137 b
\\.....o tDN 7 7 GS0 State of Illinois Department of Public Health ATTN:
Mr. Gary N. Wright, Chief Division of Nuclear Safety 535 West Jefferson Street Springfield, IL 62761 Gentlemen:
The attached IE Bulletin No. 80-16, titled " Potential Misapplication of Rosemount Inc. Models 1151 and 1152 Pressure Transmitters with Either "A" or "D" Output Codes" was sent to all the following licensees for action, and the attached IE Circular No. 80-16, titled " Operational Deficiencies in Rosemount Model 510DU Trip Units and Model 1152 Pressure Transmitters" was sent to all the fo. lowing licensees for information on June 27, 1980.
American Electric Power Service Corporation Indiana and Michigan Power Company D. C. Cook 1, 2 (50-315, 50-316)
Cincinnati Gas and Electric Company Zimmer (50-358)
Cleveland Electric Illuminating Company Perry 1, 2 (50-440, 50-441)
Commonwealth Edison Company Braidwood 1, 2 (50-456, 50-457)
Byron 1, 2 (50-454, 50-455)
La Salle 1, 2 (50-373, 50-374) j Dresden 1, 2, 3 (50-10, 50-237, 50-249)
Quad-Cities 1, 2 (50-254, 50-265)
Zion 1, 2 (50-295, 50-304)
Consumers Power Company Big Rock Point (50-155)
Midland 1, 2 (50-329, 50-330)
Palisades (50-255)
Dairyland Power Cooperative LACBWR (50-409)
Detroit Edison Company Fermi 2 (50-341) 80 0 8220N
$N 2 7 5,
State of Illinois,
Illinois Power Company Clinton 1, 2 (50-461, 50-462) i<,wa Electric Light & Power Ccmpany Duane Arnold (50-331)
Northern Indiana Public Service Company Bailly (50-367)
Northern States Power Company Monticello (50-263)
I'rairie Island 1, 2 (50-282, 50-306)
Public Service of Indiana Marble Hill 1, 2 (50-546, 50-547)
Toledo Edison Company Davis-Besse 1 (b0-3*6)
Union Electric Company Callaway 1, 2 (50-483, 50-486)
Wisconsin Electric Power Company Point Beach 1, 2 (50-266, 50-301)
Wisconsin Public Service Corporation Kewaunee (50-305)
Sincerely, kwA%d A
Helen Pappas, Chief Administrative Branch
Enclosures:
1.
IE Circular No. 80-16 cc w/encls:
Mr. D. W. Kane, Sargent & Lundy Central Files Reproduction Unit NRC 20b Local PDR NSIC TIC I
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SSINS No.: 6820 Accession No.:
UNITED STATES 8005050066 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 June 27, 1980 IE Bulletin No. 80-16 POTENTIAL MISAPPLICATION OF ROSEM0UNT INC. MODELS 1151 AND 1152 PRESSURE TRANSMITTERS WITH EITHER "A" OR "D" OUTPUT CODES Description of Circumstances The NRC has recently been advised through 10 CFR 21 reports that a potential misapplication problem exists on Rosemount Inc. Models 1151 and 1152 pressure transmitters with either "A" or "D" output codes.
The pressure transmitters are used in both pressure and differential pressure applications.
Applice.tions include pressurizer pressure monitoring (pressure transmitters) and reactor vessel level monitoring (differential pressure transmitters).
The potential misapplication problem occurs when the above specified transmitters are exposed to excessive over or reverse pressures.
These pressures can result in ambiguous signal outputs from the transmitter to control and/or indication components.
These ambiguous signals could result in erroneous control action, such F.s an open signal to a solenoid valve rather than a closed signal, or an erroneous indication signal, such as an indication in the normal operating ranac when a pressure outside the normal range actually exists. contains Rosemount Inc.'s technical description of the potential application problems for Pressure Transmitters Model 1152.
This information is applicable to Model 1151 Pressure Transmitters also.
This information includes the reasons for the maloperation of the transmitters, a typical pressure versus current output curve and examples of the results of the mal-operations.
Available information indicates that the problem was reported to each customer who was furnished the subject transmittaes by Rosemount Inc.
Actions to be Taken by Licensees of Power Reactor Operating Facilities and Holders of Construction Permits:
1.
Determine if your facility has installed or plans to install Rosemount Inc. Model 1151 or 1152 pressure transmitters with output codes "A" or "D" in any safety related application.
2.
If it is determined that your facility has the transmitters described in 1 above in any safety-related application, determine whether they can be exposed to input pressures that could result in anomalous output signals during normal. operation, anticipated transients or design bases accidents.
If the affected transmitters can be exposed to input pressures that could result in anomalous output signals, perform a worst case analysis to determine whether the anomalous signals could result in violating any
IE Bulletin No. 80-16 June 27, 1980 Page 2 of 2 design basis assumption. The safety-related application shall include control, protective or indication functions.
If any safety-related application does not conform to the above requirements address the basis for continued plant operation until the problem is resolved and provide an analysis of all potential adverse system effects which could occur as a result of a postulated pressure transmitter maloperation described in of this bulletin.
In each instance, the analysis should include the effects of postulated transmitter maloperation as it relates to indica-tion, control and protective functions.
The analysis shall address both incorrect automatic system operation and incorrect operator actions caused by erroneous indications.
Address the conformance to IEEE 279, Section 4.20 in your analysis.
Include in your analysis the following table:
a.
Complete model number.
b.
Transmitter range limits.
c.
Transmitter range setting.
d.
Range of process variable measured for (1) normal and (2) accident conditions.
e.
Values of process variable which could produce anomalous indication based upon your evaluation.
f.
Service / function.
3.
Submit a complete description of all corrective actions required as a result of your analysis and evaluations, together with the schedule for accomplishing the corrective actions.
4.
Provide the response in writing within 30 days for facilities holding an operating license or are NT0L applicants
- and within 60 days for those facilities holding construction permits.
Reports shall be submitted to the Director of the appropriate NRC Regional Office with copies forwarded to the U.S. Nuclear Regulatory Commission, Office of Inspection and Enforcement, Division of Reactor Operations Inspection (for facilities holding an operating license) or Division of Reactor Construction Inspec-tion (for facilities holding a construction permit), Washington, D.C. 20555.
- The plants that are the subject of the near term operating license reviews are: North Anna 2, Salem 2, Sequoyah 1 & 2, McGuire 1 & 2, Diablo 1 & 2, and Zimmer.
Approved by GAO, B180225 (R0072); clearance expires July 31, 1980.
Approval was given under a blanket clearance specifically for identified generic problems.
Enclosure:
Extract frcm Rosemount Inc.
letter to NRC dated June 6, 1980
D-Enct 2 to Bulletin 80-16 O
EXTRACT FROM ROSEMOUNT, INC.
LETTER TO NRC DATED JUNE 6, 1980 (i)
Name and address of the individual or individuals informing the Commission.
Not Applicable.
(ii)
Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which is affected by the potential application problem.
Rosemount Model 1152 Pressure Transmitters with output codes "A" or "D".
(iii) Identification of the firm making the report.
Rosemount Inc.
12001 W. 78th St.
Eden Prairie, MN.
55344 (iv) Nature of the potential applications problem.
Rosemount's Model 1152 pressure transmitter provides a specified linear output of 4 to 20 mA throughout the calibrated range of operation.
The transmitter output is not specified by Rosemount for pressures outside of the calibrated range of operation.
It has been observed in a limited number of transmitters that an output between 4 and 20 mA can occur with certain input pressures outside of the calibrated range.
These ambiguous outputs can occur in both an over pressure condition and a
. reverse pres'sure condition.
Both conditions arise when the center diaphragm of the pressure sensor bottoms out against either of the fixed capacitor plates.
In each case the normal capacitance signal becomes a very high capacitance signal which affects the operation of the electronic circuit.
~
For the over pressure condition, the effect of the high capacitance 1
from the sensor is a modulate 1 output on the oscillator circuit which may cause the output current of the transmitter to drop below 20 mA.
In a limited sample size, the ambiguous output during this over pressure
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condition occurred in 5% of the transmitters at ambient conditions.
Referring to the attached graph, this does not occur until the over pressure condition is > 140% of the upper range limit regardless of span.
At that point a discontinuity can occur with the output current instantaneously decreasing to less than 20 mA.
As an example of this potential applications problem, the upper range limit of a range 5 1152 differential pressure transmitter (Model 1152DP5A22) is 750"H 0.
The range of this pressure transmitter can be set from 0 to 150"H 0.
If the ambiguous output in the over pressure condition is to occ r, it will occur at 140% or more of the upper range limit or, in this c:se, at pressures > 1050"H 0-(750"H O x 1.4).
The transmitter then could give 2
an output less than 20 mA at a pressure that is, in this example, seven i
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4 times (1050"H 0 + 150"H 0) the upper range value.
Note that the 9
significantfigureforuseindeterminingthep*essureabovewhichan ambiguous output can occur is the specified upper range limit (750" H,0 in this example) not the customer selected upper range value (150"H O in this example).
2 For the reverse pressure condition, the effect of the high capacitance from the sensor is the oscillator circuit drawing more current which may cause the output current of the transmitter to exceed 4 mA.
In a limited sample size, the ambiguous output during this reverse pressure condition occurred in 55% of the transmitters at ambient conditions.
Referring to the attached graph, this does not occur until the reverse pressure condition exceeds 140% of the upper range limit regardless of the span.
At this point the output may exceed 4 mA.
As an example of this potential applications problem consider the range 5 differential transmitter in the previous paragraph.
If the ambiguous output in the reverse pressure condition is to occur, it will occur at 140% or more of the upper range limit, or in this case at reversed pressures > 1050" H 0 (750"H 0 x 1.4).
The transmitter then could give an output greater tban4mAatapressurethatis,inthisexample,seventimes(1050" H 0 + 1F9" H 0) the upper range value, but reversed.
Also note that 7
9 wTth absoluta pressure units a reverse pressure is not possible since the low pressure side of the cell is evacuated. With gage units a reverse pressure is possible only if a vacuum is present on the connected part since the low pressure side of the cell i; vented to ambient atmosphere.
Since the maximum reverse pressure would be one atmosphere, only range 3 and 4 gage units could obtain a reverse pressure exceeding 140% of the upper range limit.
Due to the effects of radiation or elevated temperature, we believe that the frequency of occurrence of the ambiguous output will be greater in a radiated or an elevated temperature environment than was experienced in our limited sample size testing, which was in a non-radiated ambient temperature environment.
After the occurrence of an ambiguous output from an over pressure or a reverse pressure condition, the transmitter will return to specified operation when the input pressure returns to the calibrated range, provided the over pressure or reverse pressure was within the maximum pressure limits specified by Rosemount.
(v)
The date on which the information of the potential applications problem was obtained.
Amended to March 6, 1980.
(vi) The nuinber und location of all in use at, supplied for, or being supplied for one or more facilities or activities subject to the regulations in this part.
Not applicable.
(vii) The corrective action recommended to negate this potential application problem.
The safety system should be analyzed in view of this supplementary report to determine if a potential application problem exists and appropriate corrections to the safety system should be implemented.
(viii) Any related to-the defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given or purchasers or licensees.
Not applicable.
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IE Bulletin No. 80-16 Enclosure June 27, 1980 RECENTLY ISSUED IE BULLETINS Bulletin Subject
-Date Issued Issued To No.
80-15 Possible Loss Of Hotline 6/18/80 All nuclear facilities With Loss Of Off-Site Power holding OLs 80-14 Degradation of Scram 6/12/80 All BWR's with an Discharge Volume Capability OL 80-13 Cracking In Core Spray 5/12/80 All BWR's with an Spargers OL 80-12 Decay Heat Removal System 5/9/80 Each PWR with an OL Operability 80-11 Masonry Wall Design 5/8/80 All power reactor facilities with an OL, except Trojan 80-10 Contamination of 5/6/80 All power reactor Nonradioactive System and facilities with an Resulting Potential for OL or CP Unmonitored, Uncontrolled Release to Environment 80-09 Hydramotor Actuator 4/17/80 All power reactor Deficiencies operating facilities and holders of power reactor construction permits 80-08 Examination of Containment 4/7/80 All power rear. tors with Liner Penetration Welds a CP and/or OL no later than April 7, 1980 80-07
-BWR Jet Pump Assembly 4/4/80 All GE BWR-3 and Failure BWR-4 facilities with an OL 79-03A Longitudinal Weld Defects 4/4/80 All power reactor In ASME SA-312 Type 304 facilities with an Stainless Steel Pipe OL or CP 80-06 Engineered Safety Feature 3/13/80 All power reactor (ESF) Reset Controls facilities with an OL
SSINS No.: 6830 Accession No.:
UNITED STATES 8005050067 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 June 27, 1980 IE Circular No. 80-16 OPERATIONAL DEFICIENCIES IN ROSEMOUNT MODEL 5100U TRIP UNITS AND MODEL 1152 PRESSURE TRANSMITTERS Description of Circumstances:
The NRC has recently been advised through a 10 CFR 21 report that operational deficiencies exist in Rosemount Inc. Model 5100U trip units and Model 1152 pressure transmitters as follows:
MODEL 510DU TRIP UNITS The 5100U trip units have common mode failures of two switches; S1 in the trip status output, LED logic circuit and 52 in the trip output logic circuit.
The trip units involved are those with serial numbers 3001 to 4203.
The 5100U units having serial numbers within this range that are not trip units are not affected. (i.e., Card Files, Readout Assemblies, Calibration Units, etc.)
Malfunction of these switches appears as an open circuit in the output logic upon receipt of an actual trip signal.
Switch (S2) failure could result in failure to automatically activate a safety function.
MODEL 1152 PRESSURE TRANSMITTERS The model 1152 pressure transmitters have a common mode failure of a capacitor 4
when the transmitter operating environmental temperature is greater than 175 F, and when the damping potentiometer is rotated clockwise.
The failure results in a decrease in transmitter output current of up to 10 percent of the correct current.
For example, when the transmitter is used in an indica-tion circuit, the parameter indication would be correspondingly lower than the correct value if the capacitor failure occurred.
The failure potentially involves all pressure transmitters with the following model designations:
J Rosemount Pressure Transmitter Models:
1152 - - - E - - T0280 1152 - - -
E. - - T0445 1152 - -
-E
- - T0400 Available information indicates that the problems outlined above have been reported to eech customer who was furnished the Model 510DU trip units and Model 1152 pressure transmitters.
IE Circular No. 80-16 June 27, 1980 Page 2 of 2 RECOMMENDED ACTION FOR LICENSEES AND HOLDERS OF CONSTRUCTION PERMITS-All licensees of nuclear power reactors and holders of construction permits should be aware of the potential problems discussed above.
It is recommended that the follo*. sing actions be taken:
1.
Determine if your facility has installed or plans to install the Rosemount Model 5100U trip units and/or the pressure transmitters described herein in any safety-related equipment.
2.
If it is determined that your facility has installed or plans to install any of the affected units described herein, contact the supplier for performance of the required modifications to the units to resolve the problems.
3.
Modifications should be performed on all affected units prior to plant operation.
If the affected units are installed in plants that are operating, the following actions are recommended for continued operation until the units are modified.
a.
510DU Trip Units A functional test verifying proper operation of the trip units should be performed.
b.
Model 1152 Pressure Transmitters
~
On pressure transmitters that are affected and that may be subjected to. operating environmental temperatures greater than 175 F, the transmitters should be operated with the damping potentiometer (R12) i in the fully counterclockwise position.
CAUTION The circuit output should be monitored to assure that no action detrimental to operation results from placing R12 in the counter-clockwise position, such as spurious tripping caused by unstable operation.
.No written response to this circular is required.
If you require additional information regarding this matter, contact the Director of the appropriate NRC Regional Office.
i i
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IE Circular No. 80-16 Enclosure
,e June 27, 1980 RECENTLY ISSUED IE CIRCULARS Circular Subject.
Date of Issued to No.
Issue 80-15 Loss of Reactor Coolant Pump 6/20/80 All power reactor Cooling and Natural Circula-facilities with an tion Cooldown OL or CP 80-14 Radioactive Contamination of 6/24/80 All holders of Power Plant Demineralized Water and Research Reactor System and Resultant Internal licensees (Operating Contamination of Personnel and Construction Permits), and Fuel Cycle licensees
/
80-13 Grid Strap Damage in 5/18/80 All holders of Reactor Westinghouse Fuel Assemblies OLs and cps 80-12 Valve-Shaft-To-Actuator Key 5/14/80 All holders of Reactor May Fall Out of Place When OLs and cps Mounted Below Horizontal Axis 80-11 Emergency Diesel Generator 5/13/30 All holders of a power Lube Oil Cooler Failures reactor OL or CP 80-10 Failure to Maintain 4/29/80 All holders of Reactor 1
Environmental Qualification OLs and cps of Equipment 80-09 Problems With Plant Internal 4/28/80 All holders of a power Communications Systems reactor OL or CP 80-08 BWR Technical Specification 4/18/80 All General Electric Inconsistency - RPS Response BWR's holding a power Time reactor OL 80-07 Problems with HPCI Turbine 4/3/80 All holders of a power Oil System reactor OL or CP 80-06 Control and Accountability 4/14/80 Medical licensees in Systems for Implant Therapy Categories G and G1 Sources 80-05 Emergency Diesel-Generator 4/1/80 All holders of a power Lubricating Oil Addition and reactor OL or CP Onsite Supply
_ _ _.