ML20086K231
| ML20086K231 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/03/1984 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Bishop T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| ANPP-28537-BSK, DER-83-39, DER83-39, NUDOCS 8401260362 | |
| Download: ML20086K231 (5) | |
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Arizona Public Service Company
- PHOENIX, ARIZONA 85036 j' '] yi' { ",
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. P.O. Box 21666 o.
January 3, 1984 C-2*
ANPP-28537-BSK/KCP U. S. Nuclear Regulatory Commission Region V' Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop, L'irector Division of Resident Reactor Projects'and Engineering Programs.
Subject:
Final Report - DER 83-39 A 50.55(e) Reportable Condition Relating to Rejectable Indications on C-E Supplied Unit 1 Reactor Coolant Pump 1A File: 84-019-026;'D.4.33.2
Reference:
A) Telephone Conversation between A. D'Angelo and R. Tucker on July 1,;1983 B) ANPP-27471, dated July 1, 1983 (Interim Report)
.C) ANPP-28119, dated October 27, 1983 (Time Extension)
Dear Sir:
Attached is our final written report of the deficiency referenced above, which has been determined to be Not Reportable under the requirements of
'10CFR50.55(e).
Very truly yoursj CL o LL(._
E. E. Van Brunt, Jr.
APS Vice President Nu: lear Projects Management ANPP Project Director EEVB/KCP:pt Attachment cc:
See Page Two
!f 8501260362 840103 PDR ADOCK 05000528
.S PDR
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Mr. T. W. Bishop DER 83-39 Page Two ec:
Richard-DeYoung, Director
' Office of_ Inspection and Enforcement U. S.' Nuclear Regulatory. Commission Washington, D. C. 20555 T. G. Woods, Jr.
C. C. Andognini J. A. Roedel
.D. B. Fasnacht.
A. C. Rogers B.-S. Kaplan 1
W. E..Ide J. Vorees J. R. Bynum D. D. Green
.P. P. Klute-A.'C. Gehr W. J. Stubblefield W. G. Bingham R.'L.
Patterson R. W. Welcher R. M. Grant D. R. Hawkinson
.L. E. Vorderbrueggen G..A.
Fiorelli S. R. Frost J. Self E. Canady Records Center Institute of Nuclear Power _ Operations 1100 circle 75 Parkway, Suite 1500 Atlanta,~GA 30339 4
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l, FINAL REPORT - DER 83-39 DEFICIENCY EVALUATION 50.55(e)
PVNGS UNIT 1 I.
Description of Deficiency On a recent re-examination and comparison between the Preservice Examination Ultrasonic (UT) data and the construction Radiographs (RT) for the Combustion Engineering (C-E) furnished Reactor Coolant Pump IA/IMRCEPOIA, two linear indications were found. The indications exist in the circumferential weld of the pump casing.
One of the RT indications found' measures thiee (3) inches long; the second measures three fourths (3/4) inches long. Both exist within a length of six (6) inches. Subsequent examinations have shown that these indications are approximately three and two tenths (3.2) inches in from the outside diameter of the casing with no perceptible through wall dimension. The base metal of the casing in this area is five and five eights (5-5/8) inches thick. The linear indications are acceptable to the ASME Section III RT acceptance criteria. A Fracture Mechanics Analysis has been performed by C-E on the casing using conservative parameters. The analysis assumed: 1) The indications have a through wall dimer.sion of three fourths (3/4); 2) The indication is a sharp crack extending around the entire circumference of the casing. This analysis showed the casing to be acceptable even under upset condicions.
II.
Analysis of Safety Implications Based on the analysis performed of the RT indications in the RCP 1A pump casing.. C-E has determined that the integrity of the primary system boundry has not been diminished and that the casing with the assuned flaw is structurally adequate for the forty year design life of the component. Thus, if left uncorrected, the subject condition would not adversely affect the safety of operations of the plant during the lifetime of the plant. Consequently, this condition is evaluated as not reportable under the requirements of 10CFR50.55(e) or 10CFR Part 21.
III.
Corrective Action 1.
C-E has conducted a 100% review of the' welds for all Reactor Coolant Pump casings for PVNGS Units 1, 2 and 3 and has found no
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other rejectable indications. Thus, the above condition is an isolated case.
2.
Although the Fracture Mechanics Analysis has shown the casing on RCP IA/IMRCEPOIA to be acceptable, C-E has committed to implement the following actions:
A.
Rework of the pump case in order to satisfy the Section III RT Acceptance Criteria.
)
Final Report - DER 83-39 Page Two Rework of the RT linear indications consists of grinding out a cavity of a size sufficient to remove the indications which were not acceptable under Section III RT criteria. An extensive analysis performed by C-E determined that such a cavity is acceptable on either die ID or the OD of the pump case. Therefore, the cavtry can be allowed to remain in the
" ground out" condition.
If an ID repair is made, cladding must be added to provide corrosion protection.
The following items were' considered in the analysis for determining the acceptablility of the cavity:
Minimum Wall Thickness The required minimum _ wall thickness of the pump casing in order to satisfy the internal pressure consideration is 1.783 inches. The resulting minimum wall for both OD and ID cavity exceeds this requirement.
Stresses in the Cavity Area In the existing stress report, stress intensities for envelope combinations of load cases for design normal upset and emergency condition and for the faulted conditions are developed and are available for the cavity area. Stress multiplication factors developed from hand and finite element solutions for a sphere with a thin spot have been established.
Multiplying the Stress Report stress intensities by these factors in the vicinity of the repair cavity and comparing the results to ASME 3ection III requirements leads to a' conclusion of adequacy. Thus, there'are no changes to the Stress Report conclusions.
A revision to the Stress Report is to be developed in order to obtain Code approval of the modified design. The actual cavity size is to be used in establishing the stress multiplying factors for the Icvisions to the Stress Report.
l Design Transients None of the load scenarios nor design transients have been modified or diminished for the analysis. Consequently, there are no operating restrictions of any kind being imposed on the modified design.
't r -
Finsi Report - DER 83-39 Page Three Section XI - Examination As a result of the rework of the RT linear' indications, a UT examination in accordance with Section XI must be perrormed.
'The outside cavity dimensions would have to include a base area of-adequate size to allow for an examination of the weld root in accordance with ASME Section XI.
An inside cavity would have no effect on a UT examination from the outside surface.
- Therefore, the inside surface would not need to be prepared to accommodate the UT requirement.
Based on2C-E's evaluation and recommendations, the RT linear indications are being reworked until they satisfy the Section III RT Acceptance Criteria by grinding out a. cavity on the inside of the pump case. After chipping and blending of the cavity is completed, an inconel clad overlay will be added for corrosion protection.
B.
Local hydro and NDE tests will be performed on the pump. The-hydrostatic test-of the' casing will be done locally by the use of hydro-dams. installed 'in the suction and discharge nozzles.
A cover will~be fitted on the casing seal housing area, and a
- portable pump will be used for applying the required-hydrostatic test pressure.
C.
NCR SM-2025 will be dispositioned as'" Repair".
3.
~ The present status of the rework on the'RT linear' indications on.
-RCP IA/IMRCEPOIA is as follows:
A.
Excavation of the IA pump casing in the area of the RT linear' indication has been completed.- The area of the ID cavity has been magnetic particle inspected and re-radiographed, both with acceptable-results meeting Section III acceptance criteria.
Hydrostatic testing of the pump to Section III-criteria has been completed. The pump, RCP IA/IMRCEPOIA, has been "N" stamped in accordance wiuth ASME Code Section III.
B.
The revised Stress Report ~has been reviewed and' accepted.
(Bechtel. log number N001-602-367.)
V C.
Cladding cf the pump cavity with inconel was completed and-examination performed in accordance with Section XI requirements.
UT Examination of the cavity satisfied the requirements of Section XI.
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