Seismic Evaluation of Wolf Creek Generating Station Structures Using Livermore Spectrum,Evaluation of Piping Sys & SupportsML20062E858 |
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Wolf Creek |
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07/23/1982 |
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BECHTEL GROUP, INC. |
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ML20062E853 |
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NUDOCS 8208100343 |
Download: ML20062E858 (5) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20210J1561999-07-29029 July 1999 Rev 0 to Wolf Creek Generating Station,Unit 1 Pressure & Temp Limts Rept ML20195E7591998-11-10010 November 1998 WCNOC Proposed PASS Function Reduction ML20249B2451998-05-18018 May 1998 Nonproprietary Version of Revised Chapters 4 & 5 to Rev 4 of HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants for Ue & Wcnoc. Chapters 4 & 5 Reflect Editorial Revs ML20248C3681998-05-18018 May 1998 Non-proprietary Version of Rev 4 to HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants ML20202F6881997-09-29029 September 1997 Evaluation of Underground Essential Svc Water Pipeline Leak ML20133F8451997-01-0808 January 1997 WCGS Quadrennial Simulator Certification Rept ML20117J0491996-05-0808 May 1996 At&T Round Cell Nuclear Util User'S Council Charter ML20100R4291996-02-28028 February 1996 Incident Investigation Team Rept, Plant Shutdown Due to Circulating Water & Essential Svc Water Intake Icing ML20100Q2031995-12-31031 December 1995 Annual SER 11 for Jan-Dec 1995 ML20091K4121995-08-22022 August 1995 Nonproprietary SE of Cycle 9 Core Reload Analysis for Wolf Creek ML20086R3281995-07-31031 July 1995 Human Interactions Evaluation Failure to Isolate Incorrect Valve Alignment During Shutdown ML20086A6531995-05-0303 May 1995 Pyrolysis Gas Chromatography Analysis of 5 Thermo-Lag Fire Barrier Samples ML20081D5481995-02-28028 February 1995 RCS Draindown Evaluation Summary Rept ML20126M1071992-12-31031 December 1992 Power Rerate Rept for Wolf Creek Generating Station ML20126B0901992-12-14014 December 1992 WCGS Simulator Certificate Data ML20116A8591992-10-31031 October 1992 Safety Evaluation & Cycle 7 TS Change Rept for Wolf Creek Generating Station ML20029A7391991-02-0606 February 1991 Economic Impact Study of Proposed KPL/KG-E Merger. ML20247F1321989-03-23023 March 1989 Post-Tensioning Sys Evaluation,Callaway Unit 1 Containment & Wolf Creek Unit 1 Containment ML20154K7881988-09-19019 September 1988 1988 Radiological Emergency Preparedness Exercise Objectives ML20195H4191988-01-14014 January 1988 Final Rept on NRC IE Bulletin 85-003 ML20147E8251987-12-31031 December 1987 Spent Fuel Storage Rack Criticality Analyses for Wolf Creek Generating Station ML20147E8361987-12-31031 December 1987 New Fuel Storage Rack Criticality Analysis for Wolf Creek Generating Station ML20237H3101987-07-16016 July 1987 Emergency Preparedness 1987 Field Exercise Scenario ML20215J0511987-06-19019 June 1987 Safety Evaluation Supporting Proposed Rev to Tech Spec 3/4.10.4 Re Reactor Coolant Loops to Replace Refs in Reactor Protection Sys P-7 Permissive w/P-10 Permissive ML20207R6911986-12-31031 December 1986 Annual Summary of Safety Evaluations Rept 2 for Jan-Dec 1986 ML20137L6381986-01-23023 January 1986 Reactor Vessel Ref Temp for Pressurized Thermal Shock ML20140A3741986-01-17017 January 1986 Final Rept of Independent Review of Environ Qualification Programs to NUREG-0588 ML20141H6201985-12-31031 December 1985 Nonproprietary Steam Generator Single-Tube Rupture Analysis for Snupps Plants Callaway & Wolf Creek ML20116E8171985-04-24024 April 1985 Final Rept:Task Analysis & Verification of Snupps Control Room ML20113A4961985-01-19019 January 1985 Rev 1 to Evaluation of Aws Field Welding on Structural & Miscellaneous Steel at Wolf Creek Generating Station, Final Rept ML20126H6031985-01-11011 January 1985 Const Self Assessment Corrective Action Evaluation ML20129D3921984-12-31031 December 1984 FSAR Commitment Compliance Study Results Rept ML20198B8321984-12-27027 December 1984 Evaluation of Aws Field Welding on Structural & Miscellaneous Steel at Wolf Creek Generating Station, Final Rept.Related Info Encl ML20133C9131984-12-27027 December 1984 Final Rept on Evaluation of Aws Field Welding on Structural & Miscellaneous Steel at Wolf Creek Generating Station. Related Documentation Encl ML20101K2821984-12-21021 December 1984 Draft Interim Justification Position for Seismic & Environ Qualification of In-Core Thermocouples,Connectors,Adaptors & Ref Junction Box (ESE-43 & ESE-44) ML20096D4721984-08-31031 August 1984 Rev 2 to Plant Recovery Core Damage Assessment Methodology ML20108B7031984-07-20020 July 1984 Monthly Progress Rept for June 1984 ML20093A3911984-06-30030 June 1984 Rev 1 to Detailed Control Room Design Review Summary Rept for Snupps, in Response to Generic Ltr 82-33,(NUREG-0737, Suppl 1) ML20086L0211984-02-0202 February 1984 Detailed Control Room Design Review Summary Rept for Snupps, in Response to Generic Ltr 82-33,NUREG-0737, Suppl 1 ML20079Q3961984-01-27027 January 1984 Rev 1 to Rept on Control of Heavy Loads ML20079G5061984-01-13013 January 1984 Rev 1 to SAR for Safety Parameter Display Sys ML20086M9611983-12-31031 December 1983 Evaluation of Containment Coating Acceptance Tests ML20079G3841983-12-31031 December 1983 Purge Valve Operability Rept,Snupps Project ML20082H9731983-11-28028 November 1983 Interim Rept on Water Seepage at Station 58 of Wolf Creek Generating Station Main Dam. W/One Oversize Figure. Aperture Card Is Available in PDR ML20071E6841983-03-10010 March 1983 Rept of Independent Review of Environ Qualification Programs to NUREG-0588 ML20064G5891982-12-31031 December 1982 Pressurizer Safety & Relief Line Piping & Support Evaluation,Callaway Unit 1 & Wolf Creek Unit ML20062E8581982-07-23023 July 1982 Seismic Evaluation of Wolf Creek Generating Station Structures Using Livermore Spectrum,Evaluation of Piping Sys & Supports ML20062K1771982-07-0101 July 1982 Essential Svc Water Sys Pump Restraint Embed Rept ML20054L4931982-06-15015 June 1982 Pressurizer & Safety Relief Line Piping & Support Evaluation & Action Plan, Interim Rept ML20052D8661982-04-30030 April 1982 to Seismic Evaluation of Wolf Creek Generating Station Structures Using Lll Spectrum. 1999-07-29
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G1521999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Wolf Creek Generating Station.With ML20211N0161999-09-0202 September 1999 Safety Evaluation Supporting GL 95-07 to License NPF-42 ML20212A0251999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Wolf Creek Generating Station.With ML20217P6451999-08-30030 August 1999 Requests Commission Approval to Publish Encl Pr,Rg & SRP & to Issue Encl Ltr to Parties of Wolf Creek Transfer Proceeding Re Disposition of Existing Antitrust License Conditions in Event OL Transfer Approved ML20210R5741999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Wolf Creek Generating Station ML20210J1561999-07-29029 July 1999 Rev 0 to Wolf Creek Generating Station,Unit 1 Pressure & Temp Limts Rept ML20210R5921999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20209H0821999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20195D5261999-06-0202 June 1999 Safety Evaluation Approving Proposed ISI Program Alternative for Limited Reactor Vessel Shell Weld Exams & Relief Request from Requirements of ASME Code,Section XI ML20210R5871999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20195K1021999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20195K1071999-04-30030 April 1999 Revised MOR for Apr 1999 for Wolf Creek Generating Station ML20206P8261999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Wcgs.With ML20196L3401999-04-30030 April 1999 Rev 1 to WCGS Cycle 11 Colr ML20210R5841999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Wolf Creek Generating Station ML20205Q0761999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Wolf Creek Generating Station.With ML20207K5991999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Wolf Creek Generating Station.With ML20207K9761998-12-31031 December 1998 Annual SER 14,for Period 980101-1231, for WCGS ML20199E6531998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Wolf Creek Generating Station.With ML20195C0011998-12-31031 December 1998 Ks City Power & Light Co 1998 Annual Rept & Financial Statements as of 981231 & 1997 for Ks Electric Power Cooperative,Inc ML20195B9901998-12-31031 December 1998 Western Resources Annual Rept for 1998 ML20198D7321998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Wolf Creek Generating Station.With ML20195H9801998-11-17017 November 1998 Safety Evaluation Supporting Proposed Changes to WCGS Radiological Emergency Response Plan ML20195E7591998-11-10010 November 1998 WCNOC Proposed PASS Function Reduction ML20195D1791998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Wolf Creek Generating Station.With ML20154L4591998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Wolf Creek Generating Station.With ML20153G2771998-09-30030 September 1998 Rev 1 to WCAP-15079, Wolf Creek Heatup & Cooldown Limit Curves for Normal Operation ML20153G2851998-09-30030 September 1998 Rev 1 to WCAP-15080, Evaluation of Pressurized Thermal Shock for Wolf Creek ML20153G2691998-09-30030 September 1998 Rev 1 to WCAP-15078, Analysis of Capsule V from Wolf Creek Nuclear Operating Corp Wolf Creek Reactor Vessel Radiation Surveillance Program ML20153G7301998-09-23023 September 1998 Special Rept 98-003:on 980814,station Entered TS 3.3.3.6, Action Statment a Due to Inoperability of RVLIS B Train. Cause Has Not Yet Been Identified.Work Order 98-202813-000 Has Been Generated ML20151W1491998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Wcgs.With ML20237B7381998-08-14014 August 1998 Special Rept 98-001:on 980615,oxygen Analyzer on Wgs Was Declared Inoperable.Wgs Oxygen Analyzer OARC-1119A Was Indicating 0 Ppm on 980814 & Fluctuated Between 200 & 900 Ppm on 980615.Completed Work Order & Declared Wgs Operable ML20237B0841998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Wolf Creek Generating Station ML20236P3441998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Wolf Creek Generating Station ML20236P3481998-05-31031 May 1998 Corrected Page of MOR for May 1998 for Wolf Creek Generating Station ML20249A0171998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Wolf Creek Generating Station ML20249B2451998-05-18018 May 1998 Nonproprietary Version of Revised Chapters 4 & 5 to Rev 4 of HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants for Ue & Wcnoc. Chapters 4 & 5 Reflect Editorial Revs ML20248C3681998-05-18018 May 1998 Non-proprietary Version of Rev 4 to HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants ML20247H0901998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Wolf Creek Generating Station ML20216J7791998-04-15015 April 1998 SER Approving Requests for Relief I1R-46 Through I1R-49 & I2R-21 Submitted by Licensee on 970523.Relief for Exam Category B-A,Item B1.12,RPV Shell Welds Deferred Until Licensee Satisfies Regulations for Augmented Rv Exam ML20216C2641998-04-0606 April 1998 SER Accepting Addl Info Re GL 92-08, Thermo- Lag 330-1 Fire Barriers, for Plant ML20216F6101998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Wolf Creek Generating Station ML20217H3491998-03-31031 March 1998 SER Accepting Operational Quality Assurance Program Description Change for Wolf Creek Generating Station ML20217H7241998-03-30030 March 1998 SER Accepting Proposed Change to Operational Quality Assurance Program for Plant ML20216G1971998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Wolf Creek Nuclear Operating Corp ML20202H0721998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Wolf Creek Generating Station ML20217G4311997-12-31031 December 1997 Western Resources 1997 Annual Rept & Financial Statements for Years Ended 971231 & 1996 for Ks Electric Power Cooperative,Inc ML20203H0151997-12-31031 December 1997 Annual Operating Rept 13 for Jan-Dec 1997 ML20217G3711997-12-31031 December 1997 Kansas City Power & Light Co 1997 Annual Rept ML20216D7771997-12-31031 December 1997 Annual SER 12 for Jan-Dec 1997, for Wolf Creek Generating Station 1999-09-30
[Table view] |
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SEISMIC EVALUATION OF WOLF CREEK GENERATING STATION STRUCTURES USING LIVERMORE SPECTRUM EVALUATION OF PIPING SYSTEMS AND SUPPORTS DECIITEL POWER CORPORATION GAITHERSBURG, MARYLAND JULY 23, 1982 8208100343 820805 PDR ADOCK 05000482 A ppg
TABLE OF cot 1TEf1TS I. Introduction II. Stress Evaluation of Piping Systems III. Stress Evaluation Results IV. Conclusion
F~
l I. Introduction i
This report is intended to outline the methodology and re-t sults of a stress evaluation performed for all site specific l Essential Service Water System Nuclear Class 3 piping at i Wolf Creek Generating Station, to determine the ef fects of increasing the current SSE ground motion design spectra g level linearly from 0.12g (zero period acceleration) to 0.15 g. The basis for the selection of a 0.15g SSE design
! spectrum, as well as its effects on the various plant build-i ings, buried piping, electrical duct banks and appurtenant structures have been discussed in a previous' report dated April 2, 1982. This report is therefore limited to the evaluation of ESWS piping and associated supports within the pumphouse and in the valvehouse adjacent to the control
- building.
i II. Stress Evaluation of Piping Systems i
The Essential Service Water System site piping servicing the Wolf Creek plant power block extends from the pumphouse located adjacent to the ultimate heat sink through the
- valvehouse and into the west wall of the control building, where it enters the power block.- The piping is buried below grade at all locations with the exception of the pumphouse l and the valvehouse. Buried ESWS piping, although not a part
- of the standard power plant, was designed for seismic loads obtained from several SNUPPS sites and is not affected by l the increased design spectra. Therefore, only the piping
- within the aforementioned structures has been considered in
! the stress evaluation.
l For analytical purposes, all piping is divided into piping i
runs individually modeled and identified with a stress problem number. Each stress problen. is modeled to include support and boundary conditions and analyzed using the applicable floor response accelerations. -All piping stress problems within the pumphouse - and valvehouse were investi-gated fo r possible stress increases resulting from higher floor response accelerations associated with a 0.15g SSE design spectrum.
SSE design accelerations used in the original dynamic analy-l sis of each piping stress problem were compared to floor i response spectral accelerations associated with the 0.15g
! design spectrum. Floor response accelerations resulting l from the original "FLUSII" analysis, as well as the fixed base analysis (see April 2, 1982 report as transmitted via KMLNRC 32-192, G. L. Koester to H. R. Denton, dated May 3, 1982) were utilized as a basis for comparison. As per pre--
vious commitments, spectral accelerations for the original
! "FLUSil" curves used in the comparison were conservatively adjusted upward by 25% to reflect the rise of 0.12g to 0.15g.
i , -
1 Where the original SSE design accelerations were not greater than the scaled " FLUSH" curves - or the fixed base analysis curves, the stress problem was reanalyzed utilizing original analysis methods as defined in the FSAR to evaluate the increased stress levels. Stress levels in the piping sup-ports and their attachments, as well as the stress levels
.t in the piping system were evaluated. The following stress problems were affected:
4 STRESS j PROBLEM NO. DESCRIPTION LOCATION 4
317 30" Supply Lines. Pumps ESWS Pumphouse A&B to pumphouse wall.
318 3" Traveling Water Screen ESWS Pumphouse i
Spray Piping. Train A 318A 3"' Traveling Water Screen ESWS Pumphouse
.l Spray Piping. Train B
- 319 3" Vent Line. Pump A ESWS Pumphouse 319A 3" Vent Line. Pump B ESWS Pumphouse 320 4" Backwash Line. ESWS Pumphouse Strainer A ,
i 320A 4" Backwash Line. ESWS Pumphouse Strainer B 322 30" Warming Line in ESWS Pumphouse Pipe Pit. Train A 322A 30" Warming Line in ESWS Pumphouse
- Pipe Pit. Train B
- 166 30" Supply Line. Train A Valvehouse 166A 30" Supply Line. Train B Valvehouse III. Stress Evaluation Results Of the eleven stress problems affected by the increased i
' floor response accelerations, four problems, (317, 318, 322 and 166) required reanalysis. Problems 319 and 320 did not
- require reanalysis since the design accelerations used in
- the original analysis exceed or are reasonably close to the l comparison basis curves. The evaluation showed that safety i
margins above those required for design, and outlined in the FSAR, exist in all. stress levels for these problems to
- ensure their integrity even with the increased spectral accelerations.
A
Problems 319A and 320A are symmetrical to problems 319 and 320. Their evaluation is therefore identical.
The reanalysis of problems 317, 318, 322 and 166 indicated all pipe stresses, although greater than the original design stresses, are within ASME code allowables. The magnitude of load increase found at all piping supports for these prob-lems, with the exception of hanger No. K-EF11-C009/011(Q),
is not significant. Hanger No. K-EP11-C009/011(Q) will be
, subjected to a significant load increase, but will not re-quire redesign, since this hanger is common to both the Callaway and Wolf Creek pumphouses and was originally de-signed for the higher Callaway loads associated with a 0.20g SSE design spectra. Problems 318A, 322A and 166A are sym- !
metrical to problems 318, 322 and 166 and are evaluated '
similarly.
IV. Conclusions All Essential Service Water System Nuclear Class 3 piping, including supports, have been reevaluated to spectral accol-erations which, when compared to those resulting from the suggested design spectra for 0.15g as per previous commit-monts, yield conservative results.
The evaluation also considered the available stress margins in the piping and support systems and indicates that no modfications would be.regoired for the piping or supports as a result of the suggested design spectra.
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