ML20205P924

Part 21 & Rev 2 to Final Deficiency Rept DER 84-08 Re Itt Barton Model 763 Transmitters Supplied by C-E Having Output Errors of -2 to -3% of Calibr Span.Defects May Affect Monitoring & Alarm Capabilities of Shutdown Cooling Sys

ML20205P924
Person / Time
Site:	Palo Verde
Issue date:	03/19/1987
From:	Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
REF-PT21-87 023-02126-JGH, 23-2126-JGH, DER-84-08, DER-84-8, NUDOCS 8704030406
Download: ML20205P924 (7)

Text

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. , . t' Arizona Nuclear Power Project .

P.O. BOX S2034

• PHOENIX, ARIZONA 85072-20b4 I i) 4 g March 19, 1987 023-02126-JGII/DRL _,.

U. S. Nuclear Regulatory Commission Region V 1450 }! aria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. D. F. Kirsch, Director Division of Reactor Safety and Projects Palo Verde Nuclear Generating Station (PVNGS) ,

Units 1, 2, 3 Docket Nos. 50-528, 529, 530

Subject:

Final Report - DER 84-08, Revision 2 A 50.55(e) and 10CFR21 Reportable Condition Relating to ITT/Barton Model 763 Transmitters do not Hect Specifications File: 87-006-216

Reference:

(A) ANPP-30027, dated July 24,1984 (DER 84-08 Final Report)

(B) ANPP-31475, dated December 14,1984 (DER 84-08 Final Report, Re v. 1)

Dear Sir:

Attached, is revision two (2) to our final written report of the Reportable Deficiency under 10CFR50.55(e) referenced above. The 10CFR21 evaluation is also included. This revision updates and further clarifies information which Aht'P feels is of a substantive nature.

Very truly yours,

b. Y y,-

J. G. Haynes Vice President Nuclear Production JGil/DRL:kp Attachments cc: See Page 2 8704030406 870319 PDR ADOCK 03000528 g PDR 9143Q/1667Q _- .

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DER 84 Final Report Rev. 2 Mr. D. F. Kirsch Director Page Two  ;

March 19,'1987 023-02126-JGH/DRL ~

cc: J. M. Taylor '

Of fice of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 A. C. Gehr (4141)'

R. P. Zinumerman (6295)

Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339

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FINAL REPORT - DER 84-08 DEFICIENCY EVALUATION 50.55(e)

ARIZONA NUCLEAR POWER PROJECT (ANPP)

PVNGS UNITS 1, 2, 3 I. Description of Deficiency Combustion Engineering (C-E), has notified the Arizona Nuclear Power Project (ANPP) that the suppressed-zero and suppressed-range ITT Barton l Model 763 pressure transmitters supplied by C-E have output errors of -2 to -3% of their calibrated span. The transmitters affected by this condition have the following project tag numbers:

1,2&3JRCEPT100X 1,263RCCPT101C 1,2&3SIAPT333 1,2&3JRCEPT100Y 1,2&3RCDFT101D 1,2&3SIAPT343 1,263JRCAPT101A 1,2&3SIBPT313 263RCAPT103 1,2&3JRCBPT101B 1,2&3SIBPT323 2&3RCBPT104 Per Combustion Engineering Specification 14273-ICE-0005, the output drift of these transmitters is not to exceed + 1.0% of the calibrated span.

The negative shift in the output of the Model 763 suppressed-zero and suppressed-range transmitters affects the monitoring of the reactor coolant and safety injection systems.

Evaluation Testing conducted by ITT Barton has determined that the root causes of this defect are:

• The creeping of a soldered joint on the link wire which connects the Bourdon tube to the strain gauge beam.

• Transverse deflection of the Bourdon tube in relation to the strain gauge.

• The location of the insulating pad which was epoxied on the strain guage beam.

There are twelve (12) pressure transmitters per unit that were affected by these problems. These transmitters are listed in the attachment and have the following plant applications.

1) Transmitters RC-PT-100X and 100Y provide pressurizer pressure inputs to C-E control grade systems. These systems are not safety-related, and therefore a 3% error is not considered safety significant.

2) Transmitters SI-PT-313, 323, 333, 343 are utilized to provide indication (only) of safety injection tank pressure only, and are not required for safe shutdown of the plant.

3) Transmitters RC-PT-101A,-101B, 101C, and 101D provide input to the l plant protections system (PPS). For these. transmitters -3.0% error could result in a non-conservative high pressurizer pressure / plant I protective system setpoint. This error combined with other anticipated errors in the PPS may delay a plant trip on high pressurizer pressure, and therefore result in a potential significant safety condition.

4) Transmitters RC-PT-103 and 104 are installed on the pressurizer and provide indication to the operator for manual action and are also used to generated permissive signals to allow alignment of the shutdown cooling system. Hence, their failure to provide accurate readings could complicate operator ability to effect a safe shutdown.

II. Analysis of Safety Implications The defects that involve the output errors in the calibrated span of the Model 763 transmitters may affect the monitoring and alarm capability of the shutdown cooling system, steam bypass system and the plant protection system.

The negative shift in output of transmitters RC-PT-101A, 101B, 101C, 101D and RC-PT-103, 104, if undetected could have impacted safe shutdown of the plant.

Based on the above, these conditions were evaluated by PVNGS as Reportable under the requirements of 10CFR50.55(e) since, if these conditions were to remain uncorrected, they could constitute a significant safety condition. The supplier, ITT Barton, has previously filed a 10CFR Part 21 report for the conditions described above.

III. Corrective Action 1he corrective action for each unit is as follows:

For Unit 1

1) RC-PT-100X and 100Y have not had design modifications implemented.

However, they are not safety-related, and can be used as is.

2) SI-PT-313, 323, 333, and 343 are not required for safe shutdown of the plant and can be used as is. No corrective action is required.

3) RC-PT-101A, 101B, 101C, and 101D are safety-related pressure transmitters. To resolve this condition, two options were considered:

a) Perform physical modification as identified above to implement ITT Barton's design changes.

A technical resolution of the " output errors in the calibrated span" defect was achieved by ITT Barton redesigning the I transmitter as follows:

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1. By welding instead of soldering the link wire to the Bourdon tube and strain gauge beam.

2. By increasing the diameter of the link wire from 7 mil to 30 mil and modifying the mounting lug on the Bourdon tube to reduce transverse deflection of the Bourdon tube in relation to the strain gauge.

3. By relocation of the strain gauge leadwire insulating pads from the strain gauge beam to the strain gauge mounting block.

b) Modify the setpoints for these transmitters in the plant protection system (PPS), to account for the negative drift l inaccuracies.

l Since qualification and other documentation for this physical modification were not available to comply with the Unit 1 fuel load schedule, the project chose to pursue the setpoint changes. Hence, I C-E evaluated this condition and revised the PPS setpoints to account for the-3% instrument error.

The revised setpoints are reflected in the C-E final setpoint report. 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.

4) For Unit 1, the two ITT Barton Model 763 pressure transmitters, tag no. RC-PT-103 and 104 were removed and replaced prior to fuel load by qualified Rosemount model 1153, series D pressure transmitters that met both the restricted range and overpressure range criteria. This work was done by DCP ISJ-RC-105.

Replacement of the ITT Barton transmitters with the Rosemount transmitters resulted in all four pressurizer pressure transmitters, l PT-103, 104, 105, and 106, being manufactured by the same company (Rosemount). The project obtained, from the NRC, a temporary (1st core) exemption to the diversity requirement for pressure sensing interlocks on redundant shutdown cooling system isolation valves.

For Unit 2 l 1

1) Same as Unit 1 i l

2) Same as Unit 1 l 3) Same as Unit 1. except transmitter no. RC-PT-101C, as indicated in 1 the attachment, had the physical modification implemented. The revised setpoint for'this modified transmitter is more conservative, and hence acceptable, from a nuclear cafety standpoint.

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4) RC-PT-103 and 104 originally from Unit 1, which were modified per CFR 14373-109 and 110 were installed in Unit 2. These transmitters now I seet the original specification requirements.

The attachment provides the status by tag number and serial number of each transmitter affected by this condition. i For Unit 3

1) Same as for Unit 1 except that'RC-PT-100Y has had the physical 4

modification implemented.

- 2) RC-PT-313, 323, 333, 343 have been modified to meet the original specification requirements.

3) RC-PT-101A, 101B, 101C, and 101D have been modified to meet the

original specification requirements. The revised setpoint for this

' modified transmitter is more conservative and hence acceptable from a j

nuclear safety standpoint.

) 4) RC-PT-103 and 104 were modified per BSN16953'to meet the original

specification requirements. l For Warehouse l l

Warehouse stock of spare Barton Transmitters are being checked to confira that all required modifications have been incorporated. (Task completion forecast 3/30/87)

IV. Attachment - ITT Barton 10CFR21 Link Wire Defect l

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DER 84-08 Attachment 1 ITT Barton 10CFR21 Link Wire Defect 4

ANPP Unit #1 ANPP Unit #2 ANPP Unit #3 Tag Number Serial Number / Status Serial Number / Status Serial Number / Status PT-100X 1032/Not Fixed 1234/Not Fixed 1263/Not Fixed FT-100Y 1033/Not Fixed 1235/Not Fixed 1803/ Fixed PT-313 1048/Not Fixed 1246/Not Fixed 1248/ Fixed PT-323 1049/Not Fixed 1247/Not Fixed 1276/ Fixed PT-333 1050/Not Fixed 1275/Not Fixed 1277/ Fixed PT-343 1051/Not Fixed 1249/Not Fixed 1278/ Fixed PT-101A 1034/Not Fixed 1236/Not Fixed 1265/ Fixed PI-101B 1035/Not Fixed 1237/Not Fixed 1266/ Fixed PT-101C 1264/Not Fixed 1036/ Fixed 1267/ Fixed PT-101D 1037/Not Fixed 1239/Not Fixed 1268/ Fixed PT-103 Rosemount 1153D 1042/ Fixed 1273/ Fixed PT-104 Rosemount 1153D 1043/ Fixed 1274/ Fixed 4

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