ML20111A863
| ML20111A863 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/14/1984 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| ANPP-31475-TDS, DER-84-08, DER-84-8, NUDOCS 8501080173 | |
| Download: ML20111A863 (4) | |
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4 RECEI 'E0 Arizona Nuclear Power Project.m P.O. BOX 52034 e PHOENIX. ARIZONA 85072-2034 I,,h f g December 14, 198inggf _
ANPP-31475-TDS/TRB U. S. Nuclear Regulatory Commission Region V 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. D. F Kirsch, Acting Director Division of Resident Reactor Projects and Engineering Programs
Subject:
Final Report - Revision 1 DER 84-08 A 50.55(e) Reportable Condition Relating To ITT/Barton Model 763 Transmitters Do Not Meet Specifications.
File: 84-019-026; D.4.33.2
Reference:
A) Telephone Conversacion between R. Dodds and T. Bradish on February 29, 1984 B) ANPP-29083, dated March 16, 1984 (Interim Report)
C) ANPP-29972, dated July 16, 1984 (Time Extension)
D) ANPP-30027, dated July 24, 1984 (Final Report)
Dear Sir:
Attached is Revision 1 to our final written report of the Reportable Deficiency under 10CFR50.55(e), referenced above. This revision updates the Condition Description and Corrective Action as requeste.d by NRR.
Very truly yours,-
CLQ qL E. E. Van Brunt, Jr.
APS Vice President Nuclear Production ANPP Project Director EEVB/TRB:db Attachment cc: See Page Two 8501080173 g43g34 DR ADOCK 05000528 g
i PDR 1 l Th-21
g L,
Mr. T. W. Bishop
' DER 84-08 Page Two.
cc:
Richard DeYoung, Director.
Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 T. G. Woods, Jr.
. D. B. Karner W. E. Ide D. :B. Fasnacht A.
C.~ Rogers L. A. Souza D. E. Fowler.
T. D. Shriver C. N. Russo J. Vorees J. R. Bynum J. M. Allen A. C. Gehr W. J. Stubblefield W. G. Bingham i
R. L. Patterson R. W. Welcher H. D. Foster D. R. Hawkinson R. P. Zimmerman D. Canady T. J. Bloom M. Matt E. A. Licitra Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 Atlanta, GA 30339 W
)
.PINAL REPORT - DER 84-08 DEFICIENCY EVALUATION 50.55(e)
ARIZONA PUBLIC SERVICE COMPANY (APS)
PVNGS UNITS 1, 2, 3 l
I.
. Description of Deficiency Combustion Engineering (C-E), has notified the Arizona Nuclear Power Project (ANPP) that the elevated / suppressed range ITT Barton Model
.763 pressure transmitters supplied by C-E have output errors of -2 to -3% of their calibrated span. The applicable project tag numbers are:
1,2&3JRCEPT100X 1,2&3RCCPT101C 1,2&351 APT 333 1,2&3JRCEPT100Y 1,2&3RDCPT101D 1,2&3S1 APT 343 1,2&3JRCAPT101A 1,2&3S1BPT313 2&3RCAPT103 1,2&3JRCBPT101B 1,2&3S1BPT323 2&3RCBPT104
~ Per Combustion Engineering Specification 14273-ICE-0005 the output i
drift of these transmitters is not to exceed +1.0% of the calibrated span.
-II.. Analysis of Safety Implications The above listed transmitters hdve the following plant applications:
l1. Transmit'ters 1, 2 and 3 JRCEPT100X and 100Y provide pressurizer
. pressure inputs to C-E control grade systems. These systems are l
~
not safety related, and therefore a 3% error is not considered safety significant.
,2. Transmitters PT313,1323, 333, and 343 are utilized for safety injection tank pressure indication only, and are not required for safe shutdown of the plant.
i
- 3.' Transmitters PT101A, -101B, -101C and -101D provide inputs to the Plant Protection System (PPS). For. these.transeitters an
. additional -3.0% error could result in a non-conservative HI pressurizer pressure / plant protective' system setpoint. This error combined with other anticipated errors in-the PPS may l.
prevent a plant trip on high pressurizer pressure,' and therefore l
result in a potential. safety significant condition.
- 4. Transmitters 2 and 3 JRCAPT103 and 2 and 3 JRCBPT104 have previously been: designated as unacceptable in DER 82-46.. The transmitters are being replaced with Rosemount Model 1153 Series D transmitters.. As a result, deficiencies with these instruments
-are no longer considered applicable to PVNGS.
L' s
i
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- Mr. T. W. Bishop ANPP-30027 Page Two Based on the above, this condition is evaluated as reportable under the requirements of 50.55(e), since if the condition were to remain uncorrected for item 3 it would represent a significant safety condition.
ITT Barton, the manufacturer of these transmitters, has filed a 10CFR Part 21 report with the NRC as notification of this deficiency.
III. Corrective Action The transmitters in items 1 and 2 will be used as is.
C-E has evaluated the condition described in item 3 and has revised the PPS setpoints to account for the -3% instrument error. The negative 3% drift error has been added algebraically to the other error components,.as shown in CEN-286(V) Rev. 00 (Page 39, Item P),
as this is a non-random error. The revised'setpoints are reflected in the C-E Final Setpoint Report, Bechtel Log Number N001-1.01-413.
The change to the PVNGS setpoints precludes the potential safety hazard as the. error is no longer considered outside the analyzed operating range. This analytical resolution enables the continued utilization of the existing transmitters without any. hardware alteration.
In order to meet C-E's original specification requirements of maximum +1.0% drift however, Barton is currently working on a physical modification to the transmitters. When this is completed the transmitters will either be repisced or refurbished and the PPS setpoints returned to their original values.
In the interim, CE has also made available the Periodic Surveillance Test error values to use during refueling calibration. If these values are found exceeded during refueling calibration, appropriate steps will be taken to factor any additional errors into the setpoint calculation. Reporting of this additional instrument error will be as required by 10CFR 50.73.
,-