ML20084L884
| ML20084L884 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/07/1984 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Bishop T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| REF-PT21-84-351-000 ANPP-29445-TDS, DER-83-76, PT21-84-351, PT21-84-351-000, NUDOCS 8405150110 | |
| Download: ML20084L884 (3) | |
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Arizona Public Service Company IB ? ? ; 19 p..
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May 7,1984 ANPP-29445-TDS/TRB I I U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria I.ane - Suite 210
- Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop, Director.
Division of Resident Reactor Projects and Engineering Programs
Subject:
Final Report - DER 83-76 A 50.55(e) Reportable Condition Relating to Auxiliary Feedwater Pump Turbine Logic File: 84-019-026; D.4.33.2
Reference:
A) Telephone Conversation between R. Dodds and R. Tucker on November 2,1983 B) ANPP-28360 dated, December 5,1983 (Interim Report)
C) ANPP-28588 dated, January 10,.1984 (Time Extension)
D) ANPP-29140 dated, March 23,1984 (Time Extension)
Dear Sir:
Attached is our final written report of the Reportable Deficiency under 10CFR50.55(e), referenced above.
(
Very tru you 7E\\ae ni E. E. Van Brunt, Jr.
APS Vice President, Nuclear ANPP Project Director EEVB/TRB:db Attachment cc:
See Page Two 8405150110 840507 PDR ADOCK 05000520 S
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v' Mr. T. W. Bishop DER 83-76 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
.B. S. Kaplan L. A. Souza i
D. E. Fowler I
J. Vorees J. R. Bynum J. M. Allen P. P. Klute A. C. Gehr
.W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher H. D. Foster D. R. Hawkinson
'L. E. Vorderbrueggen
[
G. A. Fiorelli f
S. R. Frost J. Self D. Canady i
Records Center L
Institute of Nuclear Power Operations 1100 Circle 75. Parkway, Suite 1500 Atlanta, GA 30339 a
94 FINAL REPORT - DER 83-76 DEFICIENCY EVALUATION REPORT 50.55(e)
ARIZONA PUBLIC SERVICE COMPANY PVNGS UNITS 1, 2, 3 1.
Description of Deficiency A system review of the Logic Diagram 13-J-SGL-001, Rev. 5 has revealed that the FSAR requirement, " Steam admission valve opens from the intact Steam Generator," is not satisfied.
In the'present logic for the Auxiliary Feedwater Pump Turbine (AFPT) steam supply valves, the logic actuation provides priority to Auxiliary Feedwater Actuation Signal (AFAS-1) for Steam Generator number one (SG-1) over Auxiliary Feedwater Actuation Signal (AFAS-2) for Steam Generator number two (SG-2).
If both signals are simultaneously present cr if AFAS-1 already exists upon the initiation of AFAS-2, the AFAS-1 signal takes preference and maintains SG-1 steam supply to the AFPT'until manually reset by the operator.
In case of a small line break in SG-1, the existing logic will not allow AFAS-2 to override AFAS-1, and transfer supply steam from SG-2.
Once the break in SG-1 is detected the logic must be designed to supply steam to the AFPT from the intact Steam Generator.
II.
Analysis of Safety Implications
~
The present AFPT steam aupply valve (s) logic will not allow transfer of steam supply from the ruptured SG-1 to the intact SG-2.
As a result, this will prevent the system from performing its safety fuction by'not being able to supply Auxiliary Feedwater to the intact Steam Generator.
Based on the above, this condition is evaluated as reportable under the requirements of 10CFR50.55(e), since if this condition were to remain uncorrected it would represent a significant safety condition. The PVNGS project also evaluates this condition as reportable under the requirements of 10CFR, Part 21.
III. Corrective Action A.
Logic diagram 13-J-SGL-001 will be revis'ed prior to fuel load for Units 1, 2, and'3.
B.
Design Change Packages (DCPs) ISJ-AF-052, 2SJ-AF-052 and 3CJ-AF-052 will be implemented for the required modifications prior to fuel load for Units 1, 2 and 3.
C..
SAR Change Notice 1135 has been issued to identify that AFPT steam admission valves from both Steam Generators (SG-1 and SG-2) may open on a respective AFAS-1 or AFAS-2.
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