ML19347B197
| ML19347B197 | |
| Person / Time | |
|---|---|
| Site: | Hartsville, Phipps Bend  |
| Issue date: | 09/17/1980 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | |
| References | |
| REF-PT21-80-205-008 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8010010861 | |
| Download: ML19347B197 (3) | |
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TENNESSEE VALLEY AUTHORITY
'bO-TO3b-M CHATTANOO2A TENNE 0cEE 37431 400 Chtatnut Street Tower II September 17, 1980 Mr. James P. O'Reilly, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region II - Suite 3100 101 Marietta Street Atlanta, Georgia 30303
Dear Mr. O'Reilly:
HARTSVILLE AND PHIPPS BEND NUCLEAR PLANTS - REPORTABLE DEFICIENCY -
DEFECTS IN ROSEMOUNT TRIP / CALIBRATION UNITS.
Initial notification of the subject deficiency was mad'e to NRC-0IE, Region II Inspector R. W. Wright on March 28, 1980. The first and second interim reports were submitted on April 25 and June 20, 1980, respectively.
In compliance with paragraph 50.35(e) of 10 CPR
$c-6t%kt4 tc Part 50, we are enclosing the third interim repo'rt of the. subject g.gl g.
deficiency. TVA anticipates transmitting the final report on or before January 16, 1981.
TVA considers 10 CFR Part 21 applicable to this nonconformance.
If you have any questions, please call Jim Domer at FTS 857-2014.
Very truly yours, TENNESSEE VALLEY AUTHORITY P.%24
. M. Mills, Mtnager Nuclear Regulation and Safety Enclosure cc:
Mr. Victor Stello, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 M \\ d 52f) M(e {
An Equal Opportunity Employer 4.
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ENCLOSURE HARTSVILLE AND PHIPPS BEND NUCLEAR PLANTS ( ALL UNITS)
DEFECTS IN ROSEMOUNT TRIP / CALIBRATION UNITS AND PRESSURE TRANSMITTERS 10CFR50.55(e) REPORT NO. 3 (INTERIM)
On March 28, 1980, TVA notified NRC-0IE Region II, Inspector R. W.
Wright, of a reportable deficiency under 10CFR50.55(e) regarding defects in Rosemount trip / calibration units and pressure transmitters being supplied by OE for use at the Hartsville Nuclear Plant. He was also notified on April 15, 1980, that the condition also exists for equipment being supplied for use at Phipps Bend Nuclear Plant.
These deficiencies were reported to NRC-0IE Region V, Inspector R. H.
Engleken, under 10CFR21 on March 21, 1980, by GE, both verbally and by letter MFN 065-80.
This is the third interim report on this reportable deficiency.
TVA anticipates transmitting the final report on or before January 16, 1981.
Description of Deficiency General Electric was advised by Rosemount that some of the model 510DU trip / calculation units and model 1152 pressure transmitters contain defects.
The trip unit is used in conjunction with the pressure transmitter to provide high or low trip signals.
The pressure transmitter is used for direct pressure measurement transmission or as a level sensor in conjunction with a differential pressure measuring device.
The trip has a common mode failure of two essential switches that determine the trip output logic. The malfunction open-circuits the output logic, thereby providing an inoperable signal.
As an example, when used as an ECCS water level trip unit, this can result in failure
~
to trip on low water level.
The trip units involved are those with serial numbers 3001 to 4203 The transmitter has a common mode failure of a capacitor when the transmitter operating temperature is greater than 175 F, and/or when the damping potentiometer is rotated clockwise.
The failure is manifested as a drop in transmitter output current up to 10 percent of the correct current.
As an example, when used as a pressure transmitter, this can result in transmitting reactor pressure 10 percent lower than actual. This condition applies to model 1152 Rosemount transmitters with "E" output codes and model numbers ending in 70280, T0455, and 70400.
No trip calibration units have been shipped to either Hartsville or Phipps Bend. These units are in control room panels which have not been shipped to either site.
TVA has received numerous 1152 transmitters at both Hartsville and
.... Phipps Bend..a number of which_are susceptible to the failure. modes described above.
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Sa aty Implientiena r
,Tha cxistenc3 cf tha darsets described above in both tha 510DU trip units,and the 1152 pressure transmitters could cause either inaccurate information to be transmitted to the reactor operators or failure to trip and automatically activate a safety system. These conditions could jeopardize _the safe operation of the plants.
Interim Corrective Actions CE and Rosemount has indicated they will replace the defective switches in the model 510DU trip units. Switch replacement will~be verified by GE, San Jose, for all control room panels (the only equipment containing the trip units) designated for the Hartsville.
or Phipps Bend Nuclear Plants before shipment "to TVA.
GE issued instructions to Hartsville and Phipps Bend to advise GE 4f.
the quantity of 1152 transmitters at.each site.
TVA has compiled lists of the 1152 transmitters which they have found in equipment shipped to both sites (Phipps Bend personnel loo'ked at all equipment received but listed only those transmitters to which the subject deficiency applied). GE has also compiled a list of all NSSS-supp' lied 1152 transmitters.
This list includes shipping status of each. Also, 12 model 1152 transmitters (8 at Hartsville and 4 at Phipps Bend) have been identified in STRIDE safety-related HVAC components.
These lists will be compared to be sure that all safety-related 1152 transmitters which could have this deficiency are identified so that replacement of the defective capacitor can be accomplished.
Transmitters which have been shipped to the site will be corrected by replacement of the amplifier cards containing the deficient.
capacitor.
The new amplifier cards will be provided by GE.
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Transmitters which have not yet been shipped to the sites will either be corrected at San Jose, at the vendor's shop (Rosemount)' or will be shipped to the site and corrected there.
The letter "R" will be added as a suffix to the existing serial number to indicate that the modification has been accomplished.
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PART 21 IDBUlFICATION NO. %-ws-oce COPPANY fM E N lw C + M 4 4
0 D37dT NO.,e>-saismtszdsu i
s eoMeH IMTE OF LETIER.
9 n %
DAE DISTRIBUTED 4tslto o.m.
ORIGINAL EPORT SUPPLEFBiTARY[
DISTRIBUTION:
EACTOR (R)
X REL CYCLE &
SAEGtMRDS (S)
IE FIES
[MTERIALS (FD IE FILES AD/RDI IEFILES AD/SG AD/RCI AD/FRSI AD/ROI EGIGG I,II,III,IV,V EGIONS I,II,III,IV,V EGIONS 1,II,III,lV,V
~ VSiD3R BR R-IV VrjiDOR BR, R-IV VaiD3R BR. R IV LD3 / FPA MB 5715 ffES / FCS SS-395 NRR/D3L EOD MB 7602 L0EB / FPA MG 5715 ffSS / SG SS-881 NRR/DJE AEOD MG 7602 LD3 / FPA M G 5715 NRR/DSI ASLBP E/W 450 EOD M G 7602 T
SAo/SP N B-7210A ASLBP E/W 450 NRR/DDL CENTPAL FIES 016 CBERALFILES 016 ASBP E/W 450 CBiTRAL FILES ( G RON)
CBERAL FIES' (GRON)
CSKRAL FIES 016 PDR CENTRALFILFS SS-396 CBERAL FIES (GRON)
LPDR PDR PDR TERA IPDR LPDR TERA ERA ACTION:
PRELIMINARY EVALUATION OF THE' ATTACHED REPORT INDICATES LEAD RESPONSIBILITY FOR FOLLONJP AS S}OWN BELOW: