ML18082A767
| ML18082A767 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/27/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Schneider F Public Service Enterprise Group |
| References | |
| NUDOCS 8007230173 | |
| Download: ML18082A767 (12) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 Docket Nos. 50-272 50-311 Public Service Electric and Gas Company ATTN:
Mr. F. W. Schneider Vice President - Production 80 Park Place Newark, New Jersey 07101 Gentlemen:
Jun!=! 27, 1980 The enclosed IE Bulletin No. 80-16, 11Potential Misapplication of Rosemount Inc.
Models 1151 and 1152 Pressure Transmitters with Either 11A 11 or 110 11 Output Codes, 11 is forwarded 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 Bulletih.
The enclosed IE tircular No. 80-16, 110perational Deficiencies in Rosemount Model 510DU Trip Units and Model 1152 Pressure Transmitters, 11 is forwarded *to you for information.
No written response is required.
If you desire additional information regarding these matters, please contact this office.
Sincerely,
/-2*.p:~
/ ~
H. Grier Di rector
Enclosures:
- 1.
IE Bulletin No. 80-16 with Enclosure and Attachment
- 2.
Li st 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)
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r=-_ -
Public Service Electric and Gas Company cc w/encls:
2
"\\*
F. P. Librizzi, General Manager - Electric Production E. N. Schwalje, Manager - Quality Assurance R~.L. Mittl,.Gener~l Manager - Licensing and Environment H. J. Midura, Manager - Salem Generating Station
UNIIED SIAIES NUCLEAR REGULAIORY COMMISSION OEEICE OE INSPECIION AND ENEORCEMENI WASHINGION, D.C.
20555 June 21, 1980
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SSINS No.: 6820 Accession No.:
8005050066 IE Bulletin No. 80-16 POIENIIAL MISAPPLICAIION OE ROSEMOUNI INC. MODELS 1151 AND 1152 PRESSURE IRANSMillERS WIIH EIIHER 11A 11 OR "0 11 OUI~UI CODES Description of Circumstances Ihe NRC has *recently been advised thr.ough lo CER 21 reports that a potential misapplication problem exists on Rosemount Inc. Models 1151 and 1152 pressure transmitters with either 11N1 or 110 11 output codes. Ihe pressure transmitters are used in both pressure and differenti~l pressure applications. Applications include pressurizer pres~ure 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 components. Ihese ambiguous signals could result in erroneous control action, such as an open signal to a solenoid valve rather than a closed signal 1 or an erroneous indication signal, such as an indication in the norma] operat1ng range when a pressure outside the norma] range actually exists. contains Rosemount Inc. 1s technical description of the potential application problems for Pressure Iransmitters Model 1152. Ihis information is applicable to Model 1151 Pressure Iransmitters also. !his information includes the reasons for the ma]operation of the transmitters, a typical pressure versus current o_utput 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 transmitters by Rosemount Inc.
Actions to be Taken by Licensees of Power Reactor Operating Eacilities and Holders of Construction Permits:
- 1.
- 2.
Determine if your facility has instalJed or plans to insta)) Rosemount Inc. Model 1151 or 1152 pressure transmitters with output codes 11A 11 or 110 11 in any safety-related application.
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 anoma]ous output si~nals during normal operation, anticipated transients or design bases acc1dents.
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 BuJletin 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 requi*rements 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. Ihe 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 settin~.
- 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 NIOL applicants* and within 60 days for those facilities holding construction permits.
Reports shall be submitted to the Director of the appropriate NRC Re~ional Office with copies forwarded to the U.S. Nuclear Regu]atory Commiss1on, Office of In~pection and Enforcement, Division of Reactor Operations Inspection (for facilities holdi11g an operating license) or Division of Reactor Construction Inspec-tion (for facilities holding a construction permit), Washington, O.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, 8180225 (R0012); clearance expires July 31, 1980.
ApprovaJ was given under a blanket clearance specifically for identified generic problems.
Enclosure:
Extract from Rosemount Inc.
Jetter to NRC dated June 6, 1980
- e Enc]. 1 to Bu l let i n 80-16 EXTRACT EROM ROSEMOUNT, INC.
LEITER IO 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 11A 11 or II D" *
(iii) Identification of the firm making the report.
Rosemount Inc.
12001 W. 18th St.
Eden Prairie, MN.
55344 (iv) Nature of the potential applications problem.
Rosemount 1s Model 1152 pressure transmitter provides a specified linear output of 4 to 20 mA throughout the calibrated range of operation. Ihe 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 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 signal becomes a very high capacitance signal which affects the operation of the electronic circuit.
Eor the over pressur~ 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 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 1152DP.5A22) is 750 11H2o.
The range of this pressur~ transmitter can be set !r9m o.to 150 11H,o.. If the ambiguous output 1n the over pressure cond1t1on 1s to occar, 1t will occur at 140% or more of the upper range limit or, in this case, at pressures > 1050 11H 0 (150 11H2o x 1.4).
The transmitter then could give an output less than 20 mA at a pressure that is, in this example, seven.
~~~~-*. ------... ~. =~=======~-~-*
*-------*--**----*-----*-**-*~---~---~-~--..
{v) times (1050 11H10 + 150 11H O) the upper range value.
Note that the significant ftgure for ~se in determinin9 the pressure above which an ambi9uous output can occur is the specif1ed upper range limit (750 11 H20 1n this example) not the customer selected upper range value (I50 11H2o in this example).
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 ur.per range limit, or in this case at reversed pressures > 1050 11 H?O (750'H 0 x 1.4). The transmitter then could give an outpu~ greater tnan 4 mA at a pressure that is, in this example, seven times (1050 11 H20 + 150 11 H 0) the upper range value, but reversed.
Al so note that wTth absolut~ 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 is 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 l i mi t.
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-rad.iated 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.
The date on which the information of the potential applications problem was obtained.
Amended to March 6, 1980.
- e (vi) The number and 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.
Attachment:
Graph
Attach~ent to Rosemount Inc.* Letter to NRC dated June 6, 1980 I POSSIBLE AMBIGUOUS OUTPUT 1
I OUTPUT CURRENT POSSIBLE.
. AM81GOOUS OUTPUT
,~
1------,-----:=------i,-1 __
-20mo- - - - -
~ -
- - - - -l - - - - - -
I
~-FOUR DIFFERENT CALIBRATED SPANS
-4 mo - -:-- - - - - - - ~ -- * ---- --- - - ---- -.- - - - -- - -..,...., - -...
- _...,........._ ________________________ ___, __ ~-------------------...-------.-------
- 140%
TIMES URL NEGATIVE UPPER RANGE LIMIT UPPER RANGE LIMIT -
140%
TIMES URL I
- LCN/ SIDE PRESSUFtE ) HIGH SIDE PREsSURE... (-- ---e) HIGH SIDE PRESSURE )low SIDE PRESSURE INPUT PRESSURE
- e.
IE Bulletin No. 80-16 June 21, 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 Operability 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 Release to Environment 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 A 11 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 F.ailure or BWR-4 OL 79-03A Longitudinal Weld Defects 4/4/80 All holders of a power In ASME SA-312 T~pe 304 reactor OL or Ce Stainless Steel ipe 80-06 Engineered Safety Feature 3/13/80 All holders of a power (ESE) Reset Controls reactor OL
- e.
UNITED STATES NUCLEAR REGULATORY COMMISSION OEFICE OF INSPECTION AND ENFORCEMENI WASHINGTON, D.C.
20555
- June 27, 1980 SSINS No.: 6830
. Accession No.:
8005050067 IE Circular No. 80-16 OPERATIONAL DEFICIENCIES IN ROSEMOUNI MODEL 510DU TRIP UNITS AND MODEL 1152 PRESSURE TRANSMITTERS Description of Circumstances:
The NRC has recently been advised through a 10 CER 21 report that operational deficiencies exist in Rosemount Inc. Model 510DU trip units and Model 1152 pressure transmitters as follows:
MODEL 510DU TRIP. UNIIS Ihe 510DU trip units have common mode failures of two switches; Sl in the trip status output, LED logic circuit and S2 in the trip output logic circuit. The trip units involved are those with serial numbers 3001 to 4203.
- The 510DU units havinq serial num~ers within this rang~ that a~e no~ trip.units are not affected. (1.e., Card Elles, Readout Assemblies, Cal1brat1-0n Units, etc.)
Malfunction of these switches appears as an open circuit in the output loSJiC upon receipt of ah actual trip signal. Switch (52) failure could result 1n 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 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:
Rosemount Pressure Transmitter Models:
1152 -
E -
I0280 1152 -
E -
I0445 1152 -
E -
10400 Available information indicates that the probJems outlined above have been reported to each 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 following actions be taken:
- 1.
Determine if your f aci 1 i ty has i nsta l 1 ed or pl ans to i nsta 11 the Rosemount Model 510DU 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 followin9 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~E, the transmitters should be operated with the damping potentiometer (Rl2) 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 Regiona 1 Office.
.,.L*
IE Circular No. 80-16 June 27, 1980 RECENTLY ISSUED IE CIRCULARS c*ircular 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 Contamination of Personnel OL or *CP, and fuel cycle 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 Eall 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 Oil Cooler Failures reactor OL or CP 80-10 Failure to Maintain 4/29/80 All holders of a power Environmental Qualification reactor OL or CP of Equipment 80-09 Problems With Plant Internal 4/28/80 Al 1 holde.rs of a power Communications Systems reactor OL or CP 80-08 BWR Technical Specification
. 4/18/80
- All General Electric Inconsistency* - RPS Response BWR 1s 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 GI Sources 80-05
. Emergency Diesel-Generator 4/1/80 All holders of a power Lubricating Oil Addition and reactor OL or CP Onsite Supply