Similar Documents at Surry |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML18151A1551997-11-30030 November 1997 Vols 1 & 2 of Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors, USI A-46 USNRC GL 87-02. Page 12 in Vol 1 of Incoming Submittal Not Included ML20249C0011997-11-30030 November 1997 Reactor Vessel Fluence Analysis Methodology ML18151A5241997-02-28028 February 1997 a Pilot Application of RISK-INFORMED Methods to Establish Inservice Inspection Priorities for Nuclear Components at Surry Unit 1 Nuclear Power Station ML18153A6281996-11-12012 November 1996 Simulator Certification Second Four Year Rept (1992-1996). ML18151A7101996-09-30030 September 1996 Supplemental Info for VA Power Nomad Code & Model. ML18152A1251995-09-30030 September 1995 Category 1 Root Cause Evaluation 95-12 for Undetected Loss of Unit 1 Reactor Coolant Sys Inventory While at Cold Shutdown, for Sept 1995 ML18153B2711995-03-28028 March 1995 Engineering Evaluation 22, Evaluation of Fire Rating for Ventilation Ducts in Turbine Bldg & Battery Rooms - Surry Power Station. ML18151A1831994-08-31031 August 1994 Licensing Rept for Operation W/Core Rated Power of 2,546 Mwt Surry Power Station Units 1 & 2. ML18153B4221993-07-31031 July 1993 Rev 11 to Engineering Evaluation 25, Evaluation of Existing Fire Enclosure Around Ventilation Duct,North Anna Power Station. ML18153B4211993-07-31031 July 1993 Rev 11 to Engineering Evaluation 24, Evaluation of Radiant Energy Shields,North Anna Power Station. ML18153D2981993-04-12012 April 1993 Engineering Evaluation 22,CH10-22,Rev 11, Evaluation of Fire Endurance Rating for Ventilation Ducts Coated w/Thermo- Lag,Surry Power Station. ML18152A0711993-02-0101 February 1993 NFPA Heat & Flame Evaluation of MSA Custom 4500 SCBA Using Enriched O2 Breathing Air for VA Power,Final Rept. ML18153B4231992-11-30030 November 1992 Rev 10 to Engineering Evaluation 16, Evaluation of Radiant Energy Shields,Surry Power Station. ML18151A1451992-06-15015 June 1992 Vols 1 & 2 of Control Room Design Review Reassessment Surry Power Station Units 1 & 2. ML18153C3111990-07-26026 July 1990 Decommisioning Financial Assurance Certification Rept for Surry Power Station & North Anna Power Station. ML18153C2231990-05-16016 May 1990 Analysis of Small Steam Line Break Performance W/O Low Pressurizer Pressure Safety Injection,Surry Units 1 & 2. ML18152A1531989-05-0101 May 1989 Final Summary Rept Emergency Diesel Generator Sequencing, Surry Power Station Units 1 & 2. ML18151A9661989-04-18018 April 1989 Nuclear Decommissioning Trust Agreement. ML20056A0341989-04-18018 April 1989 Nonqualified Nuclear Decommissioning Trust Amended & Restated Trust Agreement ML18153B5771988-12-29029 December 1988 Main Control Room & Emergency Switchgear Room Air Conditioning Sys. ML18151A2201988-11-30030 November 1988 Simulator Certification Submittal. ML18152A0431988-10-31031 October 1988 Ad-Hoc Endurance Test of Unprotected Steel Duct Sys Final Rept ML18152B1911988-09-0101 September 1988 Rev 1, Evaluation of Flooding of Incore Instrumentation Room Surry Power Station Unit 1. ML18153B5211988-07-26026 July 1988 Containment Liner Test Channels at Surry Power Station Units 1 & 2. ML18152A1491987-12-31031 December 1987 Rev 1 to Risk Assessment of Surry Auxiliary Feedwater Sys Tech Spec. ML18151A1351987-08-28028 August 1987 Rev 1 to SPDS SAR for VEPCO NUREG-0696 Computer Project, North Anna & Surry Nuclear Power Stations. ML18150A0211987-03-27027 March 1987 Rev 1 to Surry Unit 2 Reactor Trip & Feedwater Pipe Failure Rept. ML20207Q4601987-01-14014 January 1987 Rev 0 to Reactor Trip & Feedwater Pipe Failure Rept ML20215B4021987-01-12012 January 1987 Rev 0 to Surry Unit 2 Reactor Trip & Feedwater Pipe Failure Rept ML20215B2801986-12-29029 December 1986 Interim Rept 1, Main Feedwater Pump Suction Pipe Rupture Incident ML20207B5231986-11-30030 November 1986 Reactor Vessel Fluence & Rt/Pts Evaluations Suppl to WCAP 11016 ML18149A4491986-11-26026 November 1986 Disposal of Low Level Radioactively Contaminated Soil in Dredge Spoils Pond. ML20206C0661986-06-24024 June 1986 Draft MELPROG-PWR/MOD1 Analysis of a Tmlb' Accident Sequence ML18130A4111986-03-31031 March 1986 Crdr Final Summary Rept, Vols 1 & 2 ML20141D0751986-03-0505 March 1986 Stainless Steel Stud Cracking Analysis ML18144A0441985-11-30030 November 1985 VEPCO Surry Units 1 & 2 Safety Balance Assessment for Elimination of RCS Main Loop Pipe Break Protective Activities. ML18144A0421985-11-30030 November 1985 VEPCO Surry Units 1 & 2 RCS Loads & Component Support Margins Evaluation of Elimination of RCS Main Loop Pipe Break Protective Devices. ML18144A0431985-11-30030 November 1985 VEPCO Surry Units 1 & 2 RCS Leakage Detection Assessment for Elimination of RCS Main Loop Pipe Break Protective Devices. ML18149A1051985-09-30030 September 1985 10CFR61 Radwaste Classification Scaling Factor Evaluation. ML18142A4441985-06-0404 June 1985 Steam Generator Girth Weld Repair, Preliminary Rept ML18142A2211984-12-31031 December 1984 10CFR50 App R Rept - App A,Summary Comparison of 1984 App R Reanalysis & 1980-1982 Post-Fire Safe Shutdown Review. ML20134N8191984-08-31031 August 1984 Vol I to Administrative Controls Assessment Concerning Coating Controls at North Anna & Surry Power Stations ML20107L9251984-06-11011 June 1984 Comments on Detailed Control Room Design Review Program Plan,Surry Power Station Units 1 & 2 & North Anna Power Station Units 1 & 2 ML20134E1581984-02-28028 February 1984 Containment Integrity at Surry Nuclear Power Station ML20084G6631984-01-25025 January 1984 Snubber Rept Response to NRC Insp Repts 50-280/83-32 & 50-281/83-33 ML18141A4681984-01-20020 January 1984 Safety Parameter Display Sys SAR for NUREG-0696 Computer Project,North Anna & Surry Nuclear Power Stations. ML20087B0581984-01-20020 January 1984 VEPCO Investigative Board Preliminary Rept. W/O Cover Sheet ML18130A3951983-11-10010 November 1983 VEPCO North Anna Power Station & Surry Power Station Compliance W/10CFR50.49(b)(2). ML20117J2261983-03-31031 March 1983 Station,Vepco, 1982 Evaluation 1999-10-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr ML18152B4421999-08-27027 August 1999 LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr ML18152B4411999-08-27027 August 1999 LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage. ML18152B3771999-08-13013 August 1999 LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML18152B4181999-05-18018 May 1999 LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr ML18152B4111999-04-28028 April 1999 LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 ML18153A2741999-03-29029 March 1999 LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212 ML18153A2681999-03-19019 March 1999 LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With 990210 Ltr ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements. ML18152B7261999-01-21021 January 1999 LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With 990115 Ltr ML18152B5781998-12-16016 December 1998 LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B5811998-12-16016 December 1998 LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened ML18152B7041998-12-0101 December 1998 LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr ML18152B7081998-11-30030 November 1998 Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un. ML18152B5721998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With 981214 Ltr ML18152B6161998-11-0606 November 1998 LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable ML18152B6241998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With 981111 Ltr ML18152B6081998-10-23023 October 1998 LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely ML18152B6881998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With 981012 Ltr ML18153A3271998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2 ML18152B7811998-07-31031 July 1998 LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status ML18153A3161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2.W/980807 Ltr ML18152B7621998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Surry Power Station,Units 1 & 2.W/980707 Ltr ML18153A2581998-06-0303 June 1998 LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML18153A3141998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Surry Power Station,Units 1 & 2.W/980610 ML18152B8241998-05-22022 May 1998 LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed ML18152B8161998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2.W/980508 Ltr ML18152B7951998-04-29029 April 1998 LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6 ML18153A2511998-04-22022 April 1998 LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced ML18153A2521998-04-22022 April 1998 LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame ML20217P9941998-04-0707 April 1998 Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024 ML18153A2951998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ 980408 Ltr ML18153A2391998-03-13013 March 1998 LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued ML18153A2341998-03-0909 March 1998 LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition ML18153A2301998-03-0606 March 1998 LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs ML18153A2251998-03-0404 March 1998 LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket 1999-09-30
[Table view] |
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I CORRECTED PAGES TO REVISED REPORT ON THE
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REANALYSIS OF SAFETY-RELATED PIPING SYSTEMS SURRY POWER STATION - UNIT 1 VIRGINI A ELECTRIC AND POWER COMPANY t
i 1. Section 2, Page 2-2 Replace page in existing report.
- 2. Section 2, Table 2-1, Page 6 of 7 Replace page in existing report.
3 Sect ion 3, Page 3- I Replace page in existing report.
- 4. Section -3, Tabic 3-18, Page 2 of 3, Replace page in existing report.
- 5. Section 3, Table 3-2, Pages 8, 9, 10 Replace pages in existing report.
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- SURRY POWER STATION, UNIT 1 technique which is always more conservative than the approved SRSS method, and an SRSS technique for inter-modal combination.
Additionally, in some cases, piping is analyzed utilizing amplified response spectra (ARS) that are developed using soil structure interaction techniques (SSI-ARS). The resultant stresses and loads are used to evaluate piping, supports, nozzles, and penetrations. In accordance with the NRC letter af May 25, 1979 to Virginia Electric and Power Company (VEFCO), the seismic inertial stresses typical loads computed using the SSI-ARS have been increased by a factor of 1.5 for the DBE condition.
All 63 SHOCK 2 problems have been teanalyzed and approved by S&W Engineering l Assurance or NSC Project Management. Tatie 2-1 for the Design Basis Earthquake shows the results for these 63 stress problems. In Table 2-1, the figures for Original Total Stress, at the point of maximum total stress in the pipe, and Original Seismic Stress, at the same point, are extracted from Table 3-1 of the " Seismic Design Review Equipment and Piping, Surry Fever Station," dated September 15, 1971. The original calculations for the seismic design review report are no longer available; therefore, correlations were made to the original stresses in Table 3-1 on the basis of the MSK's.
- In Table 2-1, the columns for New Total Stress, at the point of maximum total stress in the pipe, and New Seismic Stress, at the same point, were taken from 2-2
II SURRY POWER STATION, UNIT 1 TAPLE 2-1 (Cont) -
- PIPE STRESS REEVALUATION
SUMMARY
DESIGN BASIS E RTHQUAKE
-s LIgend: .
NA : Not Available l Allowable Stress : 1.8 S h l N:w Total Stress : SLP + SDW + 1.5 SDBEI + SDBEA (f or SSI/ARS) l New Seismic = 1.5 SDBE1 (for SSI/ARS) l New Total Stress : Sgp + SDW + SDBEI
- SDBEA ( riginal ARS) l New Seismic : SDBEL ( riginal ARS)
NOTE:
- ' The original totalM and original seismicMThestresses shown in Table 2-1 were computed using new total and new seismic stresses were SHOCK 2 for the original design conditions. in some cases, different ARS's computed by the NUPIPE program More usingimportantly, different massthe models and, were based on field-verified reanalyses than the original calculations. which, in some cases, differ significantly from the original
- " piping configurationsFor this reason, the new stresses and the originalthe same physical in 1979, stresses in Table 2-1 design conditions. conditions.
are not comparable, as they do not necessarily represent J 1, 1979 table and table submitted DESCRIPTIVE NOTES (To explain differences between the August in this report): --
-- 1. The high stress point occurs on a portion of the piping with a lower temperature therefore the higher allowable.
This supports were added or modified to reduce loads on other existing supports.
s-
- 2. Pipe stress analysis performed since the August 1, 1979 submittal.
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- 3. The high stress point occurs on a portion of the piping with a higher temperature therefore the lower allowable.
4 In the original stress analysis bothAs-built spray headers wereinconsidered differences as being pipe supports caused similar two
"~ therefore only one analysis made.
separate pipe stress runs be made. This resulted in different hardware modifications due
'v to pipe support analysis.
- 5. System operating temperature revised therefore allowable stress changed accordingly.
%- 6. Problem rerun with revised building displacements.
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l SURRY POWER STATION, UNIT 1 l SECTION 3 PIPE SUPPORT RESULTS Tables 3-1A and 3-1B summarize the pipe supports evaluated in the reanalysis program. There are 944 supports (487 inside containment, 457 outside containment) on lines originally analyzed by SHOCK 2. All 944 pipe supports l
have been reanalyzed, and 136 pipe support hardware modifications have been identified. The modifications identified, due to pipe support analysis, are listed in Table 3-2.
In cases where SSI-ARS was used, the DBE seismic inertial reactions on i
supports are multiplied by 1.5. Anchor movenents are not considered in the calculation of support stresses for the DBE conditions.
l 3-1
,- -- m
' SURRY POWER STATION, UNIT 1
PIPE SUPPORT STATUS
SUMMARY
OUISIDE COsINMENT - SHOCK 2 1
No. Accep- Modifica- ,
table tions or (Evaluation No. Under Additions System
- and Total No. of Corolete) __ Evaluatiqn Recuired_ Con-ent Prob. No. Surrerts Component Cooline i - 6 26 26 l 488/480
- 4 20 20 507/481
- - 9 27 27 509A/D ,
- 1 6 6 i l 5093 2 2 509C
- 3 5 5 512
- 7 34 34 517
- 3 11 11 526C
! - 3 13 13 527A/C
- 1 15 15 612 J
- 8 14 14 614
- 6 17 17 766
- 3 6 6 1512
- 5 11 11 2526
- 4
'l 14 14 2527/2529 Containment I Vacuun
- 1 3 3 CV1 3" MP Stean 19 19 746 l'
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SURRY POWER STATION, UNIT 1
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TABLE 3-2 (Cont) .
- PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
Description of Modified Since Pre' lam Support Modification or August 21, 1979 Attributable Resolution To:
No. No. Overstressed Condition Submittal Uplift problem Note 1. Yes Seismic Replace rod hanger with sway strut. -
13 Roanalysis Uplift problem Note 1. Yes Seismic Replace rod hanger with sway strut.
14 Reanalysis U-bolt overstressed Note 1. Yes Seismic Replace with frame.
CF-2 2 Roanalysis Seismic Added weld and gusset plater.
4 Weld overstressed Note 1. Yes Reanalysis Note 1. Yes Seismic Add baseplate and shims and added 21 Improper support l 488 Reanalysis lateral restraint.
Seismic Increase weld, add brace (S1W).
22 Weld and bolts overstressed Note 1. Yes Reanalysis Weld overstressed Note 1. Yes Seismic Increase weld.
I 6 Reanalysis Note 1. Yes Seismic Replace with frame, add bracings l 509B 28 U-bolt overstressed Reanalysis and baseplate.
Structure, weld and U-bolt Note 1. Yes Seismic Removs support, add frame w/ brace.
512 3 Reanalysis overstressel Note 1. Yes Seismic Modify support, remove support, 6 Structure, weld and U-bolt Reanalysis add frame.
overstressed 8 Integral welded attachment Note 1. Yes Seismic Add pad, add braces.
Reanalysis overstressed 4 Structure and weld over- Note 1. Yes Seismic Add stanchion and slide l 612 stressed Reanalysis plates.
Seismic Add plates and shims.
~l 614 1 Structure overstressed Note 1. Yes Reanalysis ganged with H27 Pro. 8509B Seismic Replace U-bolt w/ frame, add brace.
2 Structure and U-bolt Note 1. Yes Reanalysis overstressed
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SURRY POWER STATION, UNIT 1 [
TABLE 3-2 (cont)
PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
\~
Description of Modified Since Problem Support hodification or August 21, 1979 Attributable No. No. Overstressed Condition Submitral To: Resolution 5 Support structure over- Note 1. Yes Seismic Revise IWA; add lateral brace and stressed (ganged with Reanalysis closure plate to column.
H31, Pro. #509B, H7 Pro. #512) 7 Structure and U-bolt Note 1. Yes Seismic Replace U-bolt w/ beams, add brace. -
overstressed Reanalysis l 8 Improper support Note 1. Yes Seismic Add lateral restraint.
Reanalysis -
l 9 Structure overstress Note 1. Yes Seismic Add gussets to baseplate.
Reanalysis 10 Integral welded attachment Note 1. Yes Seismic Replace exist. support w/lWA and overstressed Reanalysis frame to floor.
13 Uplift restraint required Note 1. Yes Seismic Replace vs by vc.
Reanalysis 766 5 Support structure and Note 1. Yes Support Modify support.
weld overstressed (ganged Reanalysis -
with H39, Pro. #517) 7 Support, structure over- Note L. Yes Support Modify support, stress (ganged with Reanalysis H32, Pro. #517) 8 Support uplift over- Note 1. Yes Support Modify support.
stress problem (ganged with Reanalysis H33, Pro. #517) l 9 Support veld overstressed Note 1. Yes Support Add shim plate and angle, and uplift (ganged with Reanalysis H34, Pro. #517) 14 U-bolt, welds and structure Note 1. Yes Support Remove U-bolt, add frame and brace.
overstressed Reanalysis 15 Structure and weld over- Note 1. Yes Support Add braces.
stress Reanalysis
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SURRY POWER STATION, UNZT 1 ,"
TABLE 3-2 (Cont) .'
PIPE SUPPORT HARDWARE MODIFICATION
SUMMARY
Description of Modified Since Problem Support Modification or August 21, 1979 Attributable -.
No. No. Overstressed Condition Submittal To: Resolution 2526 1 Support overstress (ganged Note 1. Yes Seismic Modify support. -
with H4 Pro. #512, H2, Reanalysis Pro. 82529) '
l 6 Integral velded attachment Note 1. Yes Seismic Modify Support.
~'
overstressed - Reanalysis 9 Uplift problem Note 1. Yes Seismic Replace rod hanger with sway Roanalysis strut.
l 18 Vertical, lateral, axial Note 1. Yes Seismic R'aplace rod hanger w/ frame, add restraint required by pipe Reanalysis Jugs to modified support, relocate stress due to H2O overstress support.
20 Integral velded attachment Note 1. Yes Seismic Rerun NUPIPE revise H18, and overstressed Reanalysis replace IWA w/(2) IWAs.
j NOTES:
- 1. Modification outside containment.
- 2. Modified prior to interim operation as required per August 22, 1979 order.
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