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Category:ARCHIVE RECORDS
MONTHYEARML20204H1461999-03-11011 March 1999
Rev 0 to C-NOME-CALC-0107, Seismic Qualification of Hot Leg Rtd,Hot Leg Pdt & Hot Leg Sampling Mnsa Hardware
ML20204H1821999-03-10010 March 1999
Rev 0 to C-PENG-CALC-021, Determination of Waterford 3 Hot Leg Seismic Response Spectra & Accelerations for Use in Analyses of Mnsas
ML20203C2261999-02-0909 February 1999
Audit Rept on Implementation of GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants, for Waterford Steam Electric Station,Unit 3 on 981214-17
ML20204H2141998-02-10010 February 1998
Rev 0 to S2-NOME-CALC-0085, Seismic Qualification of SG Pdt,Hot Leg Pdt & Hot Leg Sampling Mnsa Hardware
ML20249C8001998-02-0505 February 1998
Rev 1 to Calculation EC-M96-002, Carbon Dioxide Generator/ Oxygen Depletion in Cr
ML20204H1711998-02-0303 February 1998
Rev 0 to S-PENG-CALC-008, Nozzle Loads for Which SONGS Bottom Mounted Pzr Mnsa Was Qualified
ML20141G7031997-07-0505 July 1997
Revision B to Required Submergence to Prevent Vortexing in Csp
ML20148G6451997-05-0707 May 1997
Rev 1 to Minimum Pipe Submergence to Prevent Vortexing Calculation
ML20147G1781997-01-29029 January 1997
Water Hammer Analysis:Lpsi 'B'
ML20132H1541996-12-27027 December 1996
Press Release IV-96-63, NRC Proposes to Fine Waterford $50,000 for Design Error
ML20134D2211996-10-17017 October 1996
Press Release 96-145, NRC Asks Utility Licensees for Info on Concrete Containment Foundations at Nine Nuclear Plants
ML20148G6371995-12-0101 December 1995
Rev 0 to Minimum Pipe Submergence to Prevent Vortexing Calculation
ML20058P1081993-08-31031 August 1993
Employee Concerns Programs Insp Questionnaire
ML20086B4661993-08-20020 August 1993
Control Room Outside Air Intake Radiation Monitor Setpoint Calculation
ML20079N1061990-07-19019 July 1990
Responds to NUMARC Survey in Support of NRC License Renewal Rulemaking Questions on 316(a) & (B) Demonstration Project
ML20094F3521988-03-15015 March 1988
Calculation CENC-1805, Waterford Unit 3 Steam Generator Manways
ML20114D1471987-08-31031 August 1987
Package Consisting of Chapters 9 & 11 to Facility USARs
ML20128R1141985-07-0101 July 1985
Package of Nonconformance Repts & Drawings Re Facility
ML20140G5341985-05-0202 May 1985
Package of Correspondence Re Harassment of QC Inspectors. Portions Deleted
ML20127F8961984-12-31031 December 1984
Slide Presentation Entitled, Presentation of Operational Readiness
ML20107J1411984-10-17017 October 1984
Rs Leddick Business Card
ML20132F6651984-07-28028 July 1984
News Article Re Util Denial of Gap & Citizens for Safe Energy Claim That Util Cannot Be Trusted to Ensure Safety of Plant & That Independent Review Needed
ML20137X1171984-07-27027 July 1984
News Article Discussing Gap Suggestion That NRC Require Independent Review of Util Program to Correct Problems at Facility
ML20137X0811984-07-26026 July 1984
Press Release Discussing Gap Suggestion That NRC Require Independent Review of Util Program to Correct Problems at Facility
ML20132G3361984-07-25025 July 1984
News Release Announcing Planned Commercial Operation in First Quarter 1985 & Sept Fuel Loading.Const Costs Not Expected to Exceed Present Estimates
ML20132E2261984-06-0909 June 1984
Press Release Re NRC Receiving Pressure from Congressional Delegation Concerning Facility Licensing.Nrc 840609 Handwritten Notes Encl
ML20125C2021984-01-0303 January 1984
Package of Interview Summaries Re Quality Concerns at Facility
ML20062J5841980-10-24024 October 1980
Presentation Entitled Asymmetric Loads Slides. Related Documentation Encl
ML20062J5801980-10-24024 October 1980
Slide Presentation, Piping Preoperational Vibration Test Program Slides
ML20125C0051979-08-22022 August 1979
Viewgraph Presentation Entitled, Middle South Svcs,Inc Analysis Support Program for Arkansas Nuclear One & Waterford Unit 3
1999-03-11
[Table view]
Category:PHOTOGRAPHS & SLIDES
MONTHYEARML20127F8961984-12-31031 December 1984
Slide Presentation Entitled, Presentation of Operational Readiness
ML20062J5841980-10-24024 October 1980
Presentation Entitled Asymmetric Loads Slides. Related Documentation Encl
ML20062J5801980-10-24024 October 1980
Slide Presentation, Piping Preoperational Vibration Test Program Slides
ML20125C0051979-08-22022 August 1979
Viewgraph Presentation Entitled, Middle South Svcs,Inc Analysis Support Program for Arkansas Nuclear One & Waterford Unit 3
1984-12-31
[Table view] |
Text
1 l
Sh 1 of 4 l
O Attachment II
, Piping Preoperational Vibration Test Program Slides e
/
e' .
O 9
e 8010810[fD
/
. Sh 2 of 4 f
9 PRESENT COMMITTMENTS , .
=
PSAR SECTION 3.9 - LIMITED TO CLASS I AND Il SYSTEMS NO REFERENCE TO REG. Guloe 1.'68 e
O e
e .
b e
f
~
1
~
?
..-.....e . . . . .
hr
..m m. s i
POSSIBLE FUTURE C0t'RITTt1ENTS -
a FSAR SECTION 3.9.2 CONSONANT WITH SRP 3.9.2 SRP 3.9.2 -
PIPING VIBRATION, THERMAL EXPANSION, AND DYNAMIC EFFECT TESTING SHOULD BE CONDUCTED DURING STARTUP TESTING '
o SYSTEMS TO BE MONITORED INCLUDE: .
= ASME CODE CLASS 1, 2, AND 3 o OTHER HIGH-ENERGY SYSTEMS "ITHIN S.C.I.
STRUCTURES -
a HIGH-ENERGY SYSTEldS PORTIONS WHOSE FA URE COULD REDUC THE FUNCTION OF S.C.I.
PLANT FEATURE TO UNACCEPTABLE LEVEL
. S.C.I. PORTIONS OF MODERATE-ENERGY
. - . PIPING OUTSIDE CONTAINMENT e SUPPOP.TS AND RESTRAINTS ARE PART OF THE SYSTEMS
_ . . . . . ... L . .
Sh 4 of 4 COMPARTSON BETWEEN EBASCO APPROACH AND ANSI APPROACH FOR TRANSIENT ACCEPTANCE CPITERION EBASCO . MSI c
DETERMINE STRESS 1F < .3 7 ~
IF) 0.8 7 ~
COMPUTE U FOR ALL OTHER LOADS.(FROM ANALYSES)
NO NEED FOR FURTHER COMPUTE USAGE ,
INVESTIGATION FACTOR FROM U=1-U y
dc U"
v ,,, Aj .
y v
N; g
y WHERE N;= NUMBER OF TYPE L TRANSIENTS TIMES ~
THE EFFECTIVE NUMBER OF CYCLES WHERE N = ALLOWABLE
~
3t 4
NUMBER OF CYCLES FOR
, TYPE l-TRANSIENT CAUSING- .
~ '
STRESS S g ACCEPTANCE BASED ON NCCEPTANCEBASEDON Uy 4 0.1 ,5(Ny ) < 0.8 S 3 MORE CONSERVATIVE - BASED ON ONE TYPE CYCLEI BASED ON ALL CYCLES OF ONLY DIFFERENT TYPE ,
_ . - - . . _ . . .
