ML20203P042

Rev 0 to Crystal River 3 Pump Support Configuration Study

ML20203P042
Person / Time
Site:	Crystal River
Issue date:	04/30/1986
From:	Harrison H BABCOCK & WILCOX CO.
To:
Shared Package
ML20203P035	List: 3F0586-05, Forwards List of Documents & Meetings Since Fall of 1984 Re Exemption from GDC 4 & Snubber Optimization Plan & Related Documentation to Support 860424 Request for Amend to License DPR-72 for Snubber Optimization Approval ML20203P038 ML20203P042
References
32-1163899-01, 32-1163899-1, NUDOCS 8605060297
Download: ML20203P042 (4)

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BWNP 2069716 BS)

DOCUMENT

SUMMARY

SHEET O Babcock &Wilcox a McDermott company DOCUMENT IDENTIFIER 32-1163899-01 TITLF CR-3 PUMP SUPPORT CONFIGURATION STUDY PREPARED BY: REVIEWED BY:

NAMF H.T. ARRISQN NAMF J.J. CANNING s

SIGNATURF SIGNATUR TITLF Nk DATE ! ~ M TITLF DATE __

COST CENTER REF. PAGE(S) b o8 NEV b REV1 ER NDE ENDENC T PURPOSE AND

SUMMARY

OF RESULTS:

PURPOSE To demonstrate the effectiveness of the FPC RC pump supports.

CONCLUSION The configuration of 2 link bar supports controls the displacements of the pump and effectively takes compressive loads. This condition is dependent on the relative stiffness of the supports, RC piping, and load levels experienced by the system.

Rev 01 The purpose of this revision is to include computer run CDAK in this calculation. This is a re-run of computer run COHG contained in Rev. 00. This job was re-run with modified printout controls in order to provide additional printout. This revision is for information purposes only and does not affect the calculations or results of Rev. 00.

Affected pages: 1, 32 NOTE: The complete document consists of Revision 00 and 01.

THE FOLLOWING COMPUTER CODES HAVE SEEN USED IN THIS DOCUMENT:

CODE / VERSION / REV CODE / VERSION / REV ANSYSL4_.1C 8605060297 060502 PDR ADOCK 05000302 PAGE / OF_

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Enclosure 4 Basis for Limiting Dynamic Analyses of RC Pump Shaft Failure to Vertical Forcing Function Prepared by FPC Nuclear Engineering Staff l

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4 Os Basis for Eliminating Horizontal Forcing Function in Dynamic Analysis of CR-3 Reactor Coolant Pump Shaft Fracture The FPC decision to limit the B&W dynamic analysis to a vertical forcing function was based on the following findings. A thorough visual inspection of the pump internals did not reveal any signs of significant horizontal motion. Specifically, the vertical surfaces of the hydrostatic bearing and pump wear rings showed only minor signs of contact. This finding is reasonable based on the location of the shaft failure. The break was a clean severence of the shaft between the top of the hydrostatic bearing and the bottom of the seal cartridge. This type of fracture does not create any significant eccentric mass that would tend to cause dynamic imbalance.

The majority of the pump mass dropped on to the lower wear ring and remained at rest there throughout the transient. The remainder of the shaft continued to rotate with the motor shaft for approximately 2 1/2 minutes. This remaining section of pump shaft was relatively light in comparison to the weight of the motor rotor (700 lbf versus 34,100 lbf) and was being guided over most of its length by the pump seal cartridge. Based on these facts, we consider horizontal vibration did not play any role in the pump transient.

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