ML19321A259
| ML19321A259 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/27/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8007230096 | |
| Download: ML19321A259 (2) | |
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h UNITED STATES 8" -
~' 't NUCLEAR REGULATORY COMMISSION
,E REGION 1 C
631 PARK AVENUE
,d,4 KING OF PRUSSIA, PENNSYLVANIA 19406 June 27, 1980 Docket Nos. 50-317 50-318 Baltimore Gas and Electric Company ATTN: Mr. A. E. Lundvall, Jr.
Vice President, Supply F. O. Box 1475 Baltimore, Veryland 21203 Gentlemen:
The enclosed IE Bulletin No. 80-16, " Potential Misapplication of Rosemount Inc.
Models 1151 and 1152 Pressure Transmitters with Either "A" or "D" Output Codes,"
is forwcrded to you for action.
A written response is required.
In order to assist the NRC in evaluating the value/ impact of each Bulletin on licensees, it would be helpful if you would provide an estimate of the manpower expended in conduct of the review and preparation of the report (s) required by the Bulletin.
Please estimate separately the manpower associated with corrective actions following identification of problems through the Bulletin.
The enclosed IE Circular No. 80-16, " Operational Deficiencies in Rosemount Model 5100U Trip Units and Model 1152 Pressure Transmitters," is forwarded to you for informa tion.
No written response is required.
If you desire additional information regarding these matters, please contact this office.
Sincerely, Cl-yce H. Grier Director
Enclosures:
1.
IE Bulletin No. 80-16 with Enclosure and Attachment 2.
List of Recently Issued IE Bulletins 3.
IE Circular No. 80-16 4.
List of Recently Issued IE Circulars CONTACT:
S. D. Ebneter (215-337-5283),
80 0 7 2 3 0 Off
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Baltimore Gas and Electric 2
Company cc w/encls:
R. M. Douglass, Manager, Quality Assurance L. B. Russell, Chief Engineer T. Sydnor, General Supervisor, Operations QA R. C. L. Olson, Senior Engineer K. H. Sebra, Principal Engineer d
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b SSINS No.: 6820 Accession No.:
UNIIED SIAIES 8005050066 NUCLEAR REGULAIORY COMMISSION OEEICE DE INSPECIION AND ENE0RCEMENI WASHINGION, D.C.
20555 June 27, 1980 IE Bulletin No. 80-16 POIENIIAL MISAPPLICAIION DE ROSEMOUNI INC. MODELS 1151 AND 1152 PRESSURE IRANSMIIIERS WIIH EIIHER "A" OR "D" OUIPUI CODES Description of Circumstances Ihe NRC has recently been advised through 10 CER 21 reports that a potential misapplication problem exists on Rosemount Inc. Models 1151 and 1152 pressure transmitters with either "A" or "D" output codes.
Ihe pressure transmitters are used in both pressure and differential pressure applications.
Applications include pressurizer pressure monitoring (pressure transmitters) and reactor vessel level monitoring (differential pressure transmitters).
Ihe potential misapplication problem occurs when the above specified transmitters are exposed to excessive over or reverse pressures.
Ihese pressures can result in ambiguous signal outputs from the transmitter to control and/or indication com:onents.
Ihese ambiguous signals could result in erroneous control action, suc1 as an open signal to a solenoid valve rather than a closed signal, or an erroneouc indication signal, such as an indication in,the normal operating range when a pressure outside the normal range actually exists. contains Rosemount Inc.'s technical description of the potential application problems for Pressure Iransmitters Model 1152.
Ihis information is applicable to Model 1151 Pressure Iransmitters also.
Ihis information includes the reasons for the maloperation of the transmitters a typical pressureversuscurrentoutputcurveandexamplesoftheresultsofthemal-operations.
Available information indicates that the problem was reported to each customer who was furnished the subject transmitters by Rosemount Inc.
Actions to be Iaken by Licensees of Power Reactor Operating Eacilities 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.
Ihe 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 transiiiitter malo]eration described in of this bulletin.
In each instance, tie analysis should include the effects of postulated transmitter maloaeration as it relates to indica-tion, control and protective functions.
Ile 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.
Iransmitter range limits.
c.
Iransmitter range setting.
d.
Rangeofprocessvariablemeasuredfor(1)normaland(2) accident conditions.
e.
Values of process variable which could produce anomalous indication based u on 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 NIOL applicants
- and within 60 days for those facilities holding construction permits.
Reports shall be submitted to the Director of the appropr4te 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.
- Iheplantsthatarethesubjectoftheneartermoperatinglicensereviews 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 from Rosemount Inc.
letter to NRC dated June 6, 1980
Encl. 1 to Bulletin 80-16 EXTRACT EROM ROSEMOUNI, INC.
LETTER 10 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 b of the calibrated range of operation.y Rosemount for pressures outside 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 pressure 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 signai becomes a very high capacitance signal which affects the operation of the electronic circuit.
Eor the ever pressure condition, the effect of the high capacitance from the sensor is a modulated 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 condition occurred in 5%,of the transmitters at ambient conditions.
Referring to the attached gra pressure condition is > 140% ph, this does not occur until the over of the upper range limit regardless of scan.
At that point a discontinuity can occur with the output current i'nstantaneously 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 case, at pressures > 1050"H 0 (750"H 0 x 1.4).
The transmitter then could give 2
an output less than 20 mA at a pressure that is, in this example, seven
2-times (1050"H0+150"H0)theupperrangevalue.
Note that the 9
3 significant figure for bse in determining the pressure above which an ambiguous output can occur is the specified upper range limit (750" H 0 in this example) not the customer selected upper range value (3150"HOinthisexample).
2 For the reverse pressure condition,ircuit drawing more current whichthe effe from the sensor is the oscillator c 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 a)plications problem consider the range 5 differential transmitter in t1e previous paragraph.
If the ambiguous output in the reverse pressure condition is to occur it will occur at 140% or more of the ugper range limit, or in this ca,se at reversed pressures > 1050" H0(750H0x1.4).
The transmitter then could give an output greater 3than 4 mA at a pressure that is, in this example, seven times (1050" withabsolut$p)ressureunitsareversepressureisnotpossiblesincethe H 0 + 150" H 0 the upper range value, but reversed.
Also note that 9
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 is vented to ambient atmosphere.
Since the maximum reverse pressure would be one atmosphere, only% of range 3 and 4 gage units could obtain a reverse pressure exceeding 140 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 l
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 number and location of all in use at, supplied for, or being suppliedforoneormorefacilitiesoractivitiessubjecttothe 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,iven activity, or basic component that has been, is being, or will be g or purchasers or licensees.
Not applicable.
Attachment:
Graph
Attachnent to Rosemount Inc. Letter to NRC dated June 6,1980 c
POSSIBLE '
OUTPUT AMB IGUQUS CURRENT OUTPUT I t I
1
-20 m o- - - - - - - - - -
[------
I L
FOUR DIFFERENT 2
Call 8 RATED SPANS POSSIBLE l
AMBIGUOUS OUTPUT 1
V
_4. a _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _
Y
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l--
UPPER 14 0 %
- 14 0 %
NEGATIVE R ANGE TIMES i
TIMES UPPER LIMIT URL URL RANGE
, LIMIT LOW SIDE PRESSURE )HIGH SIDE PRESSURE (
) HIGH SIDE PRESSUREM SIDE PRESSURE INPUT PRESSURE
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IE Bulletin No. 80-16 June 27, 1980 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
80-15 Possible Loss Of Hotline 6/18/80 All holders of a power With Loss Of Off-Site Power reactor OL and fuel cycle licensees connected to Emergency Notification System 80-14 Degradation of Scram 6/12/80 All holders of a BWR OL Discharge Volume Capability 80-13 Cracking In Core Spray 5/12/80 All holders of a BWR OL Spargers 80-12 Decay Heat Removal System 5/9/80 All holders of a PWR OL Qsrability 80-11 Masonry Wall Design 5/8/80 All holders of a power reactor OL, except Trojan 80-10 Contamination of 5/6/80 All holders of a power Nonradioactive System and reactor OL or CP Resulting Potential for Unmonitored Uncontrolled ReleasetoEnvironment 80-09 Hydramotor Actuator 4/17/80 All holders of a power Deficiencies reactor OL or CP 80-08 Examination of Containment 4/7/80 All holders of a power Liner Penetration Welds reactor with a CP and/or OL no later than April 7, 1980 80-07 BWR Jet Pump Assembly 4/4/80 All holders of a BWR-3 Failure or BWR-4 OL 79-03A Longitudinal Weld Defects 4/4/80 All holders of a power In ASME SA-312 Type 304 reactor OL or CP Stainless Steel Pipe 80-06 Engineered Safety Feature 3/13/80 All holders of a power (ESE)ResetControle reactor OL
SSINS No.: 6830 Accession No.:
UNITED STATES 8005050067 NUCLEAR REGULATORY COMMISSION OEFICE OF INSPECTION AND ENE0RCEMENI WASHINGTON, D.C.
20555 June 27, 1980 IE Circular No. 80-16 OPERATIONAL DEFICIENCIES IN ROSEMOUNI MODEL 51000 TRIP UNITS AND MODEL 1152 PRESSURE TRANSMIITERS Description of Circumstances:
Ihe NRC has recently been advised through a 10 CER 21 report that operational deficiencies exist in Rosemount Inc. Model 510D0 trip units and Model 1152 pressure transmitters as follows:
MODEL 510DU TRIP UNIIS Ihe 510DU 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 i
trip units involved are those with serial numbers 3001 to 4203.
The 51000 units havin affected. (g serial numbers within this range that are not trip units are not 1.e., Card Eiles, Readout Assemblies, Calibration Units, etc.)
Malfunction of these switches appears as an o)en circuit in the output logic upon receipt of an actual trip signal.
Switc1 (52) 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 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 carameter indication would be correspondingly lower than the correct value if tie capacitor failure occurred.
The failure potentially involves all pressure transmitters with the following model designations:
Rosemount Pressure Transmitter Models:
1152 E
10280 1152 E
T0445 1152 E
T0400 Available information indicates that the problems outlined above have been reported to each customer who was furnished the Model 51000 trip units and Model 1152 pressure transmitters.
IE Circular No. 80-16 June 27, 1980 Page 2 of 2 RZCOMMENDED ACTION FOR ~ ICENSEES 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 following actions be taken:
1.
Determine if your facility has installed or plans to install the Rosemount Model 51000 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.
c b.
Mode: 1152 Pressure Transmitters Onpressuretransmittersthatareaffectedandthatmaybesubjected to operating environmental temperatures greater than 175?E, the transmitters should be operated with the damping potentiometer (R12) 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.
J IE Circular No. 80-16 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 holders of a power Cooling and Natural Circula-reactor OL or CP tion Cooldown 80-14 Radioactive Contamination of 6/24/80 All holders of a power Plant Demineralized Water or research reactor System and Resultant Internal OL or CP, and fuel cycle Contamination of Personnel licensees 80-13 Grid Strap Damage in 5/18/80 All holders of a power Westinghouse Fuel Assemblies reactor OL or CP 80-12 Valve-Shaft-To-Actuator Key 5/14/80 All holders of a power May Fall Out of Place When reactor OL or CP Mounted Below Horizontal Axis 80-11 Emergency Diesel Generator 5/13/80 All holders of a power Lube 011 Cooler Failures reactor OL or CP 80-10 Failure to Maintain 4/29/80 All holders of a power EnvironmentalQualification reactor OL or CP 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
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