ML20090G973
| ML20090G973 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/12/1984 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Bishop T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| REF-PT21-84-376-000 ANPP-29951-TDS, DER-84-23, PT21-84-376, PT21-84-376-000, NUDOCS 8407260027 | |
| Download: ML20090G973 (5) | |
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'y RECElVED tmC Arizona Public Service Company 19?? $!. I6 PN 317 July 12, 1984
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-U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 W inut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop, Director Division of Resident Reactor Projects and Engineering Programs
Subject:
Final Report - DER 84-23
-A 50.55(e) Reportable Condition Relating To Auxiliary Feedwater Pump
'B' Discharge Valve To The Condensate Storage Tank.
File: 84-019-026; D.4.33.2
Reference:
A) Telephone Conversation between S. Long and T. Bradish on April 15, 1984 B) ANPP-29493, dated May 14, 1984 (Interi: Report)
Dear Sir:
Attached is our final written report of the Reportable Deficiency under.
10CFR50.55(e), referenced above.
Very truly yours, CC, Rd._
ON P
E. E. Van Brunt, _ Jr.
-APS Vice President Nuclear Production ANPP Project Director EEVB/TRBadh Attachment cc:.See Page Two
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l Mr. T. W. Bishop DER 84-23 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 J. A. Brand A. C. Gehr W. J. Stubblefield W. C. Bingham R. L. Patterson R. W. Welcher H. D. Foster D. R. Hawkinson
.L. E. Vorderbrueggen R. P. Zimmerman S. R. Frost J. Self D. Canady
- T. J. Bloom d~
Recor a Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway,. Suite 1500 i
Atlanta, GA 30339 q
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- t FINAL REPORT - DER 84-23 DEFICIENCY EVALUATION 50.55(e)
ARIZONA PUBLIC SERVICE COMPANY (APS)
PVNGS UNITS 1, 2, 3 I..
Description of Deficiency Du' ring field testing of Auxiliary Feedwater Pump (1 AFB-P01) the yoke sleeve on the Train B Recirculation Valve (LAFB-V027) loosened and the following parts were damaged:. yoke sleeve nut, two pinion shaft bearings and two Leys. This globe valve is in the 6-inch line used for full-flow recirculation testing (see attached drawing), and the damage was due to the vibration.of the 6-inch full-flow recirculation loop during pump full-flow test. The.cause of this condition is attributed to the physical-layout of the piping and the restrictive action of Flow Orifice ~ 99.
During normal operation, since this is only a test circuit, LAFB-V027'is locked closed.
In addition to the " full-flow recirculation line, there is also a 3-inch line used for mini-flow testing of the Auxiliary Feedwater Pumps. Since a -full-flow surveillance test for the Auxiliary Feedwater Pumps is not an ASME Section IX requirement, a mini-flow test would be sufficient to meet system requirements. Hence, the l
6-inch full-flow recirculation line could be deleted.
1 II.
Analysis of Safety Implications Valve 1 AFB-V027 is open only during: full flow test so its mode of '
failure would be leakage.
It is possible that, during emergency plant operating conditions, this could result in an insufficient supply of water to the Steam Generator, thus impsiring the safety function of the Auxiliary Feedwater Pump.
i Based upon the above, this deficiency is evaluated as: reportable under 10CFR50.55(e) since, if lef t uncorrected, it would constitute a significant safety hazard.
Also, this deficiency, which relates to the design of ~ the '6-inch full-flow recirculation loop, is evaluated as reportable _under 10CFR Part 21 since it is a defect in design which could cause~a depletion in the water inventory to the' Steam Generator thereby affecting the integrity of the Reactor-Coolant boundary. This-report satisfies all reporting requirements, since full-flow recirculation testing is not used in any other.Bechtel-designed plants and this design condition is limited to the PVNGS.-
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Mr. T. W. Bishop ANPP-29951 Page Two l
III. Corrective Action A. The monthly surveillance testing of the Auxiliary Feedwater Pumps required by the Station Technical Specifications will be performed using the existing 3-inch mini-flow lines. Full flow recirculating testing of the Auxiliary Feedwater System is not required by the Technical Specifications.
B. Recirculation Valves (V018 & V027) in both Trains A and B of the Auxiliary Feedwater Pumps in Units 1, 2, and 3 will be deleted and spectacle flanges will be inserted in place of these valves to permanently block flow in the 6-inch recirculation loop. DCPs 1SM, 2SM, and 3SM-AF-062 Revision 1 have been issued to implement this change.
C. SAR Change Notice No. 1165 and Design Criteria Mannal revision request No. 869 have been initiated to document this change.
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AUXILIARY FEEDWATER PUMP
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