ML20198H412
ML20198H412 | |
Person / Time | |
---|---|
Site: | Waterford |
Issue date: | 04/07/1987 |
From: | Paul B HOLTEC INTERNATIONAL |
To: | |
Shared Package | |
ML20198H363 | List: |
References | |
HI-87114-(NP), NUDOCS 9812290337 | |
Download: ML20198H412 (4) | |
Similar Documents at Waterford | |
---|---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20195C3041999-05-28028 May 1999
[Table view]Annual Rept on ABB CE ECCS Performance Evaluation Models ML20204H1401999-03-23023 March 1999 Rev 1 to Engineering Rept C-NOME-ER-0120, Design Evaluation of Various Applications at Waterford Unit 3 ML20204H2451999-03-22022 March 1999 Rev 2 to C-NOME-SP-0067, Design Specification for Mechanical Nozzle Seal Assembly (Mnsa) Waterford Unit 3 ML20204H1231999-03-22022 March 1999 Rev 1 to Design Rept C-PENG-DR-006, Addendum to Cenc Rept 1444 Analytical Rept for Waterford Unit 3 Piping ML20198H3911998-07-14014 July 1998 Non-proprietary Rev 5 to HI-961586, Thermal-Hydraulic Analysis of Waterford-3 Spent Fuel Pool ML20248E7781998-06-0101 June 1998 Annual Rept on ABB CE ECCS Performance Evaluation Models ML20198H4681998-05-20020 May 1998 Non-proprietary Rev 1 to HI-981942, Independent Review of Waterford Unit 3 Spent Fuel Pool Cfd Model ML20247A3891998-05-0101 May 1998 SG Eddy Current Examination (8th Refueling Outage) ML20199F5831998-01-29029 January 1998 Errata Change Pages for Rept HI-971628,for Section 8.6.1.2 & Table 8.1.Change Pages Submitted to Assure Consistency Between LAR & Calculations Performed for SFP Structural Analysis ML20198H4641998-01-28028 January 1998 Non-proprietary Rev 1 to HI-91700, Dynarack Validation Manual ML20141G7081997-07-0505 July 1997 To Rept on Vortexing in Condensate Storage Pool ML20140F1491997-04-16016 April 1997 Rev 3 to 10CFR50.59 Safety Evaluation ML20137G2141997-03-27027 March 1997 Non-proprietary Version of Licensing Rept for Reracking of Waterford 3 Sfps ML20094H4141995-11-0303 November 1995 Thermo-Lag Installed to Tested Fire Barrier Evaluation (GL 86-10 Evaluation) ML20086T3561995-07-31031 July 1995 Individual Plant Exam for External Events ML20094H4001995-05-30030 May 1995 Pyrolysis Gas Chromatography Analysis of 3 Thermo-Lag Fire Barrier Samples ML20078F1001995-01-31031 January 1995 Summary of Waterford 3 Criticality Safety Analysis for Fuel Enrichments Above 4.1 W/O U-235 Taking Credit for Fixed Burnable Poisons ML20078Q2951994-11-0909 November 1994 3 Ses Tsc/Osc Tabletop 4,941109 ML20078Q3111994-11-0707 November 1994 3 Ses EOF Tabletop 4,941107 ML20078Q2851994-10-12012 October 1994 3 Ses Tsc/Osc Tabletop 3,941012 ML20078Q3051994-10-10010 October 1994 3 Ses EOF Tabletop 3,941010 ML20078Q2741994-09-20020 September 1994 3 Ses Tsc/Osc Tabletop 2,940920 ML20078Q3021994-08-15015 August 1994 3 Ses EOF Tabletop 2,940815 ML20078Q2731994-05-25025 May 1994 3 Ses Tsc/Osc Tabletop 1,940525 ML20078Q3001994-05-23023 May 1994 3 Ses EOF Tabletop 1,940523 ML20062M1441993-12-29029 December 1993 Section 6.0 of Development of RCS Pts...& Recommended Surveillance Withdrawal Schedule for Waterford Unit 3 ML20059D3971993-10-31031 October 1993 Rev 0 to Development of RCS Pressure Temp Limits for 20 EFPYs (Fluence = 2.29 X 10(19) n/cm(2)) & Recommended Surveillance Withdrawal Schedule for Waterford Unit 3, Final Rept ML20198H3711991-11-12012 November 1991 Non-proprietary HI-91700, Dynarack Validation Manual ML20086C4241991-09-0505 September 1991 Design Engineering Program Assessment Executive Summary ML20073K8451991-03-31031 March 1991 Entergy Nuclear Performance Rept,Mar 1991 ML20199F5531991-03-31031 March 1991 Chin Shan Analyses Show Advantages of Whole Pool Multi-Rack Approach, from Nuclear Engineering International,Mar 1991 ML20072R2261991-03-20020 March 1991 3 Plant Ref Simulator Certification Package ML20056A7301990-06-30030 June 1990 Basemat Monitoring Program Special Rept 3 ML20246P2561989-07-31031 July 1989 Compliance W/10CFR50.62 Reduction of Risk from ATWS Events ML20245J5071989-07-31031 July 1989 Unit 3 Control Element Assembly Drop Time Tech Spec Change Justification ML20155E1311988-10-31031 October 1988 Compliance W/10CFR50.62,Reduction of Risk from ATWS Events ML20207L2881988-09-30030 September 1988 Basemat Monitoring Program,Special Rept 2, from Inception to Aug 1988 ML20155B7181988-09-0909 September 1988 Rev 1 to Louisiana Power & Light Co Response to US-NRC Bulletin 88-005 ML20154D0571988-09-0909 September 1988 Actions Completed by Louisiana Power & Light Co ML20151F1771988-06-30030 June 1988 1987 SALP Progress Rept Updated June 1988 ML20195G8941988-06-20020 June 1988 MSIV Guide Rail Failure Final Rept ML20151B7901988-03-31031 March 1988 1987 SALP Progress Rept W3P87-1746, Emergency Preparedness Exercise1987-10-14014 October 1987 Emergency Preparedness Exercise ML20234C1501987-07-31031 July 1987 Basemat Summary Rept ML20214M5571987-05-27027 May 1987 Draft Waterford 3 Nuclear Plant Island Structure Basemat Summary Rept. W/Two Oversize Figures ML20198H4061987-04-30030 April 1987 Non-proprietary HI-87113, Evaluation of Fluid Flow for In- Phase & Out-of-Phase Rack Motions ML20198H4421987-04-0707 April 1987 Non-proprietary HI-87112, Fluid Flow in Narrow Channels Surrounding Moving Rigid Bodies ML20198H4121987-04-0707 April 1987 Non-proprietary HI-87114, Estimated Effects of Vertical Flow Between Racks & Between Fuel Cell Assemblies ML20198H4371987-01-14014 January 1987 Non-proprietary HI-87102, Study of Non-Linear Coupling Effects ML20215N4601986-10-0101 October 1986 Program to Perform Confirmatory Analyses,Nuclear Plant Island Structure Basemat:Results of Analyses 1999-05-28 Category:TEXT-SAFETY REPORT MONTHYEARML20217F2891999-10-13013 October 1999
[Table view]Drill 99-08 Emergency Preparedness Exercise on 991013 05000382/LER-1999-014, :on 990910,reactor Shutdown Due to Loss of Controlled bleed-off Flow,Occurred.Caused by Rotating Baffle failure.Two-piece Rotating Baffle of Original Design Was Located & Installed,In Order to Repair RCP 2B1999-10-12012 October 1999
ML20199C9101998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Waterford 3.With ML20198F4691998-12-21021 December 1998 Safety Evaluation Supporting Amend 147 to License NPF-38 ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20206N4131998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Waterford 3.With ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program 1999-09-30 |
Text
!
l l
l t
l l
s ESTIMATED EFFECTS OF VERTICAL FLOW BETWEEN RACKS AND BETWEEN FUEi. CELL ASSEMBLIES by h
B. Paul Director, Dynamic Systems and Structures Holtec International Holtec Report No. HI-87114 Holtec Project 61200 April', 1987 1
w 9812290337 981223
?
PDR ADOCK 05000382 P DR ;;,,
Qpi.
P
"o----
HOLTEC INTERNATIONAL
'd REVIEW AND CERTIFICATION LOG 1
DOCUMENT NAME:
Estimated Effects of Vertical Flow l
between Racks and Between Fuel Cell Assemblies HOLTEC DOCUMENT I.D. NO.
HI-87114 HOLTEC PROJECT NO.
61200 CUSTOMER / CLIENT:
Pacific Gas and Electric REVISION BLOCK l
l ISSUE NO.
AUTHOR REVIEWER QA MANAGER APPROVED
- l
& DATE
& DATE
& DATE BY & DATE l
l 6'M\\h C,
/#. Ykt =
l ORIGINAL ISSUE @M 'l-T l Mp c%
- V M"'N5.
.p, a e j
ML D v: 4 O
4h/M REVISION 1 44 l
REVISION 2 I
h NOTE:
Signatures and printed names are required in the review block.
- Must be Section Director or the President.
l Th2.s document conforms to the requirements of the design specification and the applicable sections of the governing codes.
This document bears the ink stamp of the professional engineer who is certifying this documer.t.
l b0449
/
l Professional Engineer SEAL s *;
Y bli N) e
. s ~ - s q.,
,.m..,.
f' M"!S.T'A PAL SINH}{ d b
\\t%\\..c.;7~-'
.s.
togos:t A%..{v.*J e
=A e,
ep
'8
- - - - + >
IL f
ABSTRACT l
l In a previous report (Reference 1), fluid flows between racks and between fuel i
cell assemblies were calculated on the assumption that all flow took place in a horizontal plane. In the present report, an estimate is made of the actual.
l horizontal flux, q,, in the presence of vertical flow, g.
For the case y
1 l
I l
l l
REMAINDER OF DOCUMENT IS PROPRIETARY j
AND IS EXCLUDED FROM THIS NON-PROPRIETARY VERSION i
l i
r' '
i
l ENCLOSURE 7
- (Non-Proprietary Version of Attachment 5 to W3F1-98-0016, dated 1/29/98) l l
t