|
---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20205L0541999-04-0101 April 1999 Nonproprietary Replacement Pages to HI-91738,consisting of Section 5.0, Thermal-Hydraulic Analysis ML17059C5501999-01-31031 January 1999 Rev 0 to MPR-1966(NP), NMP Unit 1 Core Shroud Vertical Weld Repair Design Rept. ML20151P1751998-06-16016 June 1998 Rev 0 to SIR-98-067, Evaluation of NMP Unit 2 Feedwater Nozzle-to-Safe End Weld Butter Indication (Weld 2RPV-KB20, N4D) ML20198B4991998-05-15015 May 1998 Non-proprietary Replacement Pages for Attachment F to Which Proposed to Change TS 5.5, Storage of Unirradiated & Sf ML17059C1681998-03-19019 March 1998 Revised Niagara Mohawk Powerchoice Settlement Document for NMPC PSC Case Numbers 94-E-0098 & 94-E-0099, Vols 1 & 2 ML18040A3301998-02-28028 February 1998 Rev 0 to Technical Rept 97181-TR-03, EPR Testing of Boat Samples from Core Shroud Vertical Welds V-9 & V-10 at NMP Unit 1. ML17059B9051998-02-28028 February 1998 NMP Unit 1 Boat Samples Analyses Part Iii:Tension Tests, RDD:98:55863-004-000:01 ML17059B9061998-02-28028 February 1998 Non-proprietary Rev 0 to GE-NE-523-B13-01869-113NP, Assessment of Crack Growth Rates Applicable to NMP Unit 1 Vertical Weld Indications. ML17059B9071998-02-28028 February 1998 Rev 0 to Technical Rept 97181-TR-02,Vol 1 to Interpretive Metallurgical Rept on Core Shroud Vertical Weld Boat Samples from NMP Unit 1. ML20217F1201997-09-30030 September 1997 Rev 1 to Boat Sample Analyses at NMP Unit 1 ML17059B6771997-08-11011 August 1997 Rev 0 to Evaluation of Overlay for RWCU Weld 33-FW-22. ML17059B5901997-06-30030 June 1997 Rev 0 to Metallurgical Evaluation of Failed Shroud Tie Rod Lower Spring Contact Wedge Latches, for June 1997 ML17059B4861997-04-30030 April 1997 Non-proprietary Rev 0 to GE-NE-523-B13-01869-043, Assessment of Vertical Weld Cracking on NMP1 Shroud. ML17059B4881997-04-30030 April 1997 Non-proprietary Rev 0 to Gene B13-01739-40, Shroud Repair Anomalies NMP1,RF014. ML17059B5111997-04-30030 April 1997 Non-proprietary Version of Rev 1 to GE-NE-523-B13-01869-043, Assessment of Vertical Weld Cracking on NMP1 Shroud. ML17059B4891997-04-30030 April 1997 Non-proprietary Rev 0 to Gene B13-01739-22, Design Rept for Improved Shroud Repair Lower Support Latches. ML17059B5071997-04-30030 April 1997 Final Rept, Analysis of Nine Mile Point Unit 1 Shroud Weld V9 & Weld V10 Cracking. ML17059B4931997-04-0303 April 1997 Core Shroud Cracking Evaluation. ML17059B2411996-08-13013 August 1996 NMP-1 Core Shroud Repair Mod Summary Rept. ML17059B2441996-08-13013 August 1996 Non Proprietary Version of Suppl 1 NMP-1 Seismic Analysis, Core Shroud Repair Mod. ML17059B2421996-08-13013 August 1996 Suppl 4 NMP-1 Shroud Repair Hardware Stress Analysis. ML17059B2431996-08-0909 August 1996 Rev 4 to Stabilizer Installation. ML18040A1801996-08-0101 August 1996 Rev 5 to Reactor. Drawings Encl ML17059B1221996-04-29029 April 1996 Nonproprietary Core Shroud Repair 270 Degree Tie Rod Assembly Assessment. ML17059B0091995-11-29029 November 1995 NMP Unit 2 Safety Evaluation Summary Rept. ML18040A1671995-09-29029 September 1995 NMP Nine Mile Point Unit 1 Nuclear Power Station Rept of RPV FW & CRD Return Line Nozzle Exams Performed for NUREG-0619...at Culmination of Refueling Outage 13 Which Ended on 950404. ML17059B0181995-01-20020 January 1995 Feedwater Nozzle Analysis. ML18040A1621995-01-16016 January 1995 Rev 2 to 25A5583, Shroud Repair Hardware. ML17059A5781994-12-31031 December 1994 Non-proprietary Version of Final Rept Plant-Specific Charpy Shift Model for Nine Mile Point Unit 1. ML17059A5041994-12-31031 December 1994 Unit 2 Safety Evaluation Summary Rept 1994. ML18040A2971994-10-31031 October 1994 Final Rept Entitled Fracture Mechanics Assessment of Nine Mile Point Unit 1 Shroud H4 Weld. ML18040A2271994-08-19019 August 1994 Nuclear Engineering Rept, Nine Mile Point Unit 1 Shroud Cracking Safety Assessment for GL 94-03. ML17059A3611994-07-0606 July 1994 Emergency Action Level Verification & Validation Rept. ML17059A3531994-06-10010 June 1994 Ny State EAL Upgrade Project Nine Mile Point Unit 1 EAL Generation Package. ML17059A3551994-06-10010 June 1994 Eals. ML17311A0181994-05-13013 May 1994 New York State EAL Upgrade Project Verification & Validation Rept. ML17059A3401994-04-30030 April 1994 Rev 0 to Nine Mile Point Unit 1 Feedwater Nozzle Fatigue Evaluation. ML17059A3411994-04-30030 April 1994 Rev 0 to Nine Mile Point Unit 1 CRD Return Nozzle Fatigue Evaluation. ML17059A0881993-12-31031 December 1993 Safety Evaluation Summary Rept 1993. ML17059A0311993-08-31031 August 1993 Elastic Plastic Fracture Mechanics Assessment...Nine Mile Point,Unit 1:Response to NRC RAI Re GL 92-01 ML18038A7381993-03-17017 March 1993 Upper Shelf Energy Uncertainty Analysis for Nine Mile Point Unit 1 Beltline Welds Final Rept ML18038A7351993-02-22022 February 1993 Final Rept, Elastic-Plastic Fracture Mechanics Assessment of Nine Mile Point Unit 1 Beltline Plates for Service Level C & D Loadings. ML18038A7361993-02-19019 February 1993 Beltline Plate Orientation Determination, Final Rept ML18037A0831992-12-16016 December 1992 Elastic-Plastic Fracture Mechanics Assessment of Nine Mile Point Unit 1 Beltline Plates for Svc Level a & B Loadings. ML18038A7261992-11-19019 November 1992 Technical Response to SE by NRR Related to Proposed Deferment of Torus Mods, Nmp,Nmpns,Unit 1 Docket 50-220 ML17056C1091992-10-29029 October 1992 NMP Unit 2 Safety Evaluation Summary Rept. ML18038A7141992-10-16016 October 1992 Final Rept Entitled, Elastic-Plastic Fracture Mechanics Assessment of Nine Mile Point Unit 1 Beltline Plates for Service Level a & B Loadings. ML18038A5181992-06-12012 June 1992 Response to GL 92-01 for Nine Mile Point Unit 1. ML17056B4781991-12-31031 December 1991 Unit 2 Safety Evaluation Rept 1991. ML18038A3741991-09-0909 September 1991 Rev 1 to Root Cause Rept for Exide UPS 1A,B,C,D & G Trip Event of 910813. Electrical Fault on B Phase Main step-up Transformer Occurred Due to Improper Design.Logic Power Supply for Subj UPS Units to Be Modified 1999-04-01
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G2161999-10-15015 October 1999 Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217K4631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Nine Mile Point, Unit 1.With ML20216J9251999-09-30030 September 1999 Suppl to Special Rept:On 990621,11 Containment Hydrogen Monitoring Sys Chart Recorder Was Indicating Below Normal Operating Range.Caused by Excessive Wear on Valve Body & Discs of Bypass Pump.Sample Pump Replaced ML20212F7301999-09-21021 September 1999 Special Rept:On 990907,CR Operators Declared 12 Containment Hydrogen Monitoring Sys Inoperable for Planned Maint.Cause of Low Flow Condition Was Determined to Be Foreign Matl. Replaced Sample Pump Valve Discs ML20212B9081999-09-14014 September 1999 Special Rept:On 990901, 12 Containment Hydrogen Monitoring Sys Was Declared Inoperable for Planned Maint.Caused by Planned Maint Being Performed as Corrective Action.Check Valves with O Rings Were Replaced ML20212C4601999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Nine Mile Point Nuclear Station,Unit 1.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 ML20210U4591999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Nine Mile Point, Unit 1.With ML20209D0291999-07-0202 July 1999 Special Rept:On 990621,operator Identified That Number 11 Hydrogen Monitoring Sys (Hms) Chart Recorder Was Indicating Below Normal Operating Range.Cause Indeterminate.Licensee Will Complete Troubleshooting of Subject Hms by 990709 ML20210B9081999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Nine Mile Point Unit 1.With ML20209F8811999-06-0808 June 1999 Rev 1 to NMP Unit 1 COLR for Cycle 14 ML20207G2261999-06-0707 June 1999 SER Accepting Proposed Mod to Each of Four Core Shroud Stabilizers for Implementation During Current 1999 Refueling Outage at Plant,Unit 1 ML20196E2111999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Nmp,Unit 1.With ML20207B0241999-05-18018 May 1999 Safety Evaluation of Topical Rept TR-107285, BWR Vessel & Intervals Project,Bwr Top Guide Insp & Flaw Evaluation Guidelines (BWRVIP-26), Dtd December 1996.Rept Acceptable ML20206U5351999-05-17017 May 1999 SER Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant, Units 1 & 2 ML20196L2301999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Nmp,Unit 1.With ML20205L0541999-04-0101 April 1999 Nonproprietary Replacement Pages to HI-91738,consisting of Section 5.0, Thermal-Hydraulic Analysis ML20205S5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for NMP Unit 1.With ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207G2671999-03-0101 March 1999 Special Rept:On 990315,Nine Mile Point,Unit 1 Declared Number 12 Containment Hydrogen Monitoring Sys Inoperable. Caused by Degraded Encapsulated Reed Switch within Flow Switch FS-201.2-1495.Technicians Replaced Flow Switch ML20204C9971999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Nine Mile Point,Unit 1.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML17059C5501999-01-31031 January 1999 Rev 0 to MPR-1966(NP), NMP Unit 1 Core Shroud Vertical Weld Repair Design Rept. ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20199K9331998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20210R8441998-12-31031 December 1998 1998 Annual Rept for Energy East ML20206P2391998-12-31031 December 1998 Special Rept:On 981222,operators Removed non-TS Channel 12 Drywell Pressure Recorder & Associated TS Pressure Indicator from Svc.Caused by Intermittent Measuring Cable Connection in non-TS Recorder Circuitry.Replaced Cable ML20206P2421998-12-30030 December 1998 Special Rept:On 981219,number 12 Hydrogen Monitoring Sys (Hms) Was Declared Inoperable When Operators Closed Valve 201.2-601.Caused by Indeterminate Failure of Valve 201.2-71. Supplemental Rept Will Be Submitted After Valve Is Repaired ML20198M3571998-12-23023 December 1998 Special Rept:On 981210,operators Declared Number 11 Inoperable,Due to Failure of CR Chart Recorder.Caused by Inverter Board in Power Supply Circuitry of Recorder Due to Component Aging.Maint Personnel Replaced Failed Inverter ML20198D9361998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Nine Mile Point,Unit 1.With ML20155E2001998-11-0202 November 1998 Safety Evaluation Approving NMP 980227 Request for Extension of Reinspection Interval for Core Shroud Vertical Welds at NMP1 from 10,600 Hours to 14,500 Hours of Hot Operation ML20195J4141998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20154D8401998-10-0505 October 1998 Safety Evaluation Accepting Proposed Changes Related to PT Limits in Plant,Unit 1 TSs ML20154P1821998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20153B2001998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Nmpns,Unit 1.With ML20237C6351998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20236T5911998-07-20020 July 1998 LER 98-S01-00:on 980618,security Force Member Left Nine Mile Point,Unit 2 Vehicle Gate Unattended Without Ensuring,Gate Alarm Had Been Reactivated.Caused by Inadequate Work Practice.Vehicle Gate Alarm Was Activated ML18040A3491998-07-0202 July 1998 LER 98-017-00:on 980602,control Room Ventilation Sys Was Declared Inoperable.Caused by Original Design Deficiency. Mod Designed,Tested & Implemented Prior to Startup from RF06 to Correct Design deficiency.W/980702 Ltr ML20236Q1701998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Nine Mile Point Nuclear Station,Unit 1 ML17059C1011998-06-24024 June 1998 LER 98-014-00:on 980525,noted Differences Between Actual Valve Weights & Weights Shown on Engineering Drawings.Caused by Vendor Failing to Provide Accurate Valve Weights.Revised Valve Drawings & Associated Calculation,Per 10CFR21 ML20151P1751998-06-16016 June 1998 Rev 0 to SIR-98-067, Evaluation of NMP Unit 2 Feedwater Nozzle-to-Safe End Weld Butter Indication (Weld 2RPV-KB20, N4D) ML18040A3451998-06-0404 June 1998 LER 98-004-01:on 980302,TS Required LSFT of Level 8 Trip of Main Turbine Was Missed.Caused by Knowledge Deficiency of EHC Sys.Revised Applicable LSFT Procedures Prior to Refueling Outage 6.W/980604 Ltr ML20249B4971998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20198B4991998-05-15015 May 1998 Non-proprietary Replacement Pages for Attachment F to Which Proposed to Change TS 5.5, Storage of Unirradiated & Sf ML20247R1141998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20217B0621998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Nine Mile Point Nuclear Station,Unit 1 ML17059C1681998-03-19019 March 1998 Revised Niagara Mohawk Powerchoice Settlement Document for NMPC PSC Case Numbers 94-E-0098 & 94-E-0099, Vols 1 & 2 ML20217F4341998-03-19019 March 1998 SER Related to Proposed Restructuring New York State Electric & Gas Corp,Nine Mile Point Nuclear Station,Unit 2 ML17059B9051998-02-28028 February 1998 NMP Unit 1 Boat Samples Analyses Part Iii:Tension Tests, RDD:98:55863-004-000:01 1999-09-30
[Table view] |
Text
25A5585 SH WO.
GENm&iar&wrgy REV.2 1
EIS IDENT: SHROUD REPAIR REVISION STATUS SHEET DOCUMENT TITLE SHROUD REPAIR HARD'WARE TYPE: DBSIGN SPECIFICATION FMF: NINE MILEPOlNT 1 MPLNO: PRODUCT
SUMMARY
SECTION 7 DENOTES CHANGE THIS ITEM IS OR CONTAINS A SAFETY-RELATED ITEM YES REVISION Q NO + EQUIP CLASS CODE P RM-01607 11/11/94 J. L. TROVATO 12/19/94 RJA RM-01832 CHK BY: J. L. TROVATO 2 J;L. TROVATO J~~ f g )g95 RJA CONTROL ISSUE CN-02080 CHK BY: J. L. TROVATO PRINTS TO MADE BY APPROVALS GENBRAI. ELECTRIC COMPANY 175 CURTNER AVENUE J. L. TROVATO 10-24-94 W. F. FARRELL 11-09-94 SAN.IOSB CALIFORNIA95125 CHKD BY: ISSUED J. L. TROVATO 11-09-94 R.J. AHMANN11-11-94 CONT ON SHEET 2 MS-WORD (Ol/16/95 2:28 PM) 950S08003i 950i23
,PDR ADOCK
' 05000220
'.P", .PAR
25A5588 se No. 2 GENacfaar &wrgy REV. 2
- 1. SCOPE 1.1 This document defines the design and performance requirements for stabilizers and H8 support brackets for the core shroud which will functionally rcplacc wclds Hl through H8. A sketch of the welds and their nomenclature is given in Figure 1 ASME Code requirements
~
arc given in thc document of Paragraph 2.1.l.b.
- 2. APPLICABLE DOCUMENTS 2.1 . Thc following documents form a part of the specification to the extent specified herein.
2.1.1
- a. Liquid Penetrant Examination ESOYP22
- b. Shroud Repair, Code Design Specification 25A5586
- c. Fabrication of Shroud Stabilizer 25A5584
- d. Nine Mile Point 1 Shroud Data 105E1418A 2.1.2 c. Documents under thc following identities are to bc used with this specification:
- a. Reactor Components 888HA7I5
- b. Essential Components 22A8041 2.2 . Thc following documents form a part of this specification to thc cxtcnt specified herein.
2.2.1
- a. Section III,Appendices, 1989 Fdition.
- b. Section III, Subsection NB, 1986 Edition
- c. Section III, Subsection NG, 1988 Edition with Addenda through Summer 1984.
- d.Section IX, Welding and Brazing Qualifications, 1989 Edition
25A558S sH No. S REV. 2 2,5 QFSAR, Nine Mile Point 1, Rcv. 12
- b. NMPC, Licensing Basis Seismic Analysis Data for the Reactor Building, NMPl (Soil Stiffness Data), Faxed on 8/27/94
- c. NMPC, Licensing Basis Reactor Building Analysis data extracts, Faxed on 8/27/94 and 9/6/94
- d. NMPC, Licensing Basis Reactor Support Structure Dynamic Analysis Data Extracts, Faxed on 9/9/94 c Design Criteria Document, "Criteria for Seismic Analysis", ¹ DCD-115, Rev, 0 S. GENERAL DESCRlPTION 3,1 Thc purpose of thc shroud stabilizers and H8 weld support brackets is to structurally replace welds Hl through H8, as defined in thc document of paragraph 2.l.ld, Wclds Hl through H6B are all of thc circumferential wclds in the shroud. Weld H7 is thc shroud.to shroud support ring weld. Weld H8 is thc bimetallic weld of thc shroud support ring to thc shroud support conc. These wclds werc required to both vertically and horizontally support the core top guide, core support plate, and shroud head; and to prevent core flow bypass into thc downcomer region. The core top guide and core support plate horizontally support thc fuel assemblies and maintain thc correct fuel channel spacing. thereby assuring control rod I
insertion.
- 4. REQUIREMENTS 4.]
4.1.1 The Shroud Stabilizer and H8 Support Brackets are not classified as ASME Code components. Howcvcr, material properties for the design analysis of these items shall bc obtained from the document in Paragraph 2.2.l,a, and welding qualification shall be performed in accordance with the document in Paragraph 2.2.l.d. Thc nomenclature for stress intensity used in this document is thc sarnc as that used in the documents of Paragraph 2.2.l.b and 2.2.l.c. The Shroud Stabilizers and H8 Support Brackets shall mcct or. exceed thc original construction requirements for the shroud.
4.2 4.2.1 Ail structural analysis shall be performed in accordance with thc criteria given in the document in Paragraph 2.S.a and the additional requirements of this specification. All of the load combinations given in Paragraph 4.5.5 shall bc shown to satisfy the primary and
25A5588 sH No. 4 RF.V. 2 secondary stress limits given in Section XVl, A,2.7 of the document listed in Paragraph 2.8.a with values of SFmin as dcflned in Paragraph 4.3,6. The appropriate SFmin values have been incorporated into the allowable stress intensity values given in Paragraphs 4.2.1.1 and 4.2.1.2.
4.2.1.1 Thc primary stresses {Pm, Pl, and Pl+ Pb) in the existing shroud, during normal and upset events, shall be shown to be less than Sm, 1.5Sm, and 1.5Sm rcspcctivcly. During emergency events, the allowable stresses are increased by a factor of 1.5 times the values for normal and upset events. During faulted events, the allowable stresses are increased by a factor of 2.0 times the values for normal and upset events, 4.2.1.2 The stresses (Pm, Pm+ Pb, and Pm+ Pb+ Q) in the repair hardware, during normal and upset events, shall be shown to bc less than Sm, 1.5Sm, and 3.0Sm respectively. During emergency events, the allowable primary stresses are increased by a factor of 1.5 times thc values for normal and upset events. During faulted events, thc allowable primary strcsscs arc incrcascd by a factor of 2.0 times the values for normal and upset events. Secondary stresses are notlirnited during emergency and faulted events.
4.2,2 The values of Sm and Sy for fnconcl alloy X-750 at operating temperature (defined in paragraph 4.3.8.1) are 47,500'psi and 92,800 psi, rcspcctivcly. The Sm values for the Inconel SB168 shroud cone and thc 304 stainless steel shroud arc 23,300 psi and 15,800'psi, rcspcctivcly. For all other applications, the values of Sm and Sy as well as any other required ntaterial property shall bc obtained from thc document in Paragraph 2.2,1.a. If Certifie Material Test Reports (CMTRs) are available, the value of Sm may bc dctcrmincd using the tncthod in Appendix Ill of the document in Paragraph 2,2.l,a, 4.2.3 The maximum permanent deflectio of any point on thc shroud adjacent to either thc li2 or the H3 weld shall bc less than 2.l inches divided by SFmin, during all of the load combinations specified in Paragraph 4,3.5, The maximum permanent dcflcction of any point on the shroud adjacent to either the HGA or HGB weld shall bc less than 0.75 inch divided by SFn~in, during all of the load co>nbinations spcciflcd in Paragraph 4.8.5. The maximum transient clastic dcflcction during the seismic event adjacent to cithcr the H6A or H6B weld shall bc less than 1.68 inch diridcd by SFmin spccifled in Paragraph 4.8.6.
4.3.1 +~]. Thc shroud repair hardware shall be designed to horizontallysupport the top guide, core support plate, the fue) assemblies and theshroud head. Thc shroud repair shall bc designed to prevent vertical displacement of the shroud and shall provide its vertical support in the event of a complete H8 weld failure. The design features controlling thc horizontal and upward movements may bc diffcrcnt than thc features providing thc vertical support. The shroud repair shall be designed for a design life of 25 years (thc remaining design life of thc plant, plus possible life cxtcnsion beyond the current operating license), to include 20 Ffrcctive Full Power Years. All shroud repair hardware shall be designed so that they can be removed and rcplaccd. This is to provide full access to thc annulus area for
25A5588 SH NO. 5
~
REV. 2 possible future inspections and/or maintenance/repair activities that may prove necessary in the future.
5 " * 'P""5'" ' 5"' '" P' bending deflection greater than the deflection resulting from the limiting design upset condition, exclusive ofseismic events.
Th "5 '
5 5% for the springs.
4.3,S
.P..l ~. Th*5 55 *5 *5 h* P5 h d *'55'F.
operating temperature is 515-585'F. Operating temperature may be used for emergency and faulted evaluations.
h 4.8,8.2 RadiaQgn. The maximum neutron radiation level at the shroud repair hardware is 4x10" neutrons/cm>/sec, which will have no effect on material properties. This will'not afTect the properties of the shroud repair hardware over the remaining life of the plant.
4.8.4,1 The shroud repair hardware shall restrain the shroud during all of the load combinations in Paragraph 4.8.5. The allowable permanent deflection is dependent on the safety signiTicance of the portion of the shroud under consideration. The allowable permanent deflectio for those portions of the shroud, which affect control rod insertion, is given in Paragraph 4,2.S. For the portion of the shroud above H2, the allowable deflection is 2.8 inches, which assures that the core spray lines are not impacted by the shroud.
4.8.4.2 Tlie shroud repair hardware must provide features which facilitate handling during installation. The upper and lower springsshall be movable without removing the tie rod and without welding, in order to permit inspection of the reactor pressure vessel with GERIS 2000 and ABB RF012 tool.
4.8.4,8 All parts shall be captured and held in place by a method that will last for the design life given in Paragraph 4.8.1.
4.8.4.4 The design shall be removable to accommodate the installation of the recirculation nozzle plugs.
4.S.4.5 The design shall address the feasibility of installing the Overhead Grid Spray Sparger.
25A5585 sH No. 6 REV. 2
..5 ~Th*f 'l*d*li ~
- h h d p i I d The only earthquake is a design basis carthquakc {DBE), rcfcrcncc 2.S.a, Section iV-7.1.
Event Dead Prcssure OBE DBE WelSht (~ DBE)
Normal Vpsct Nortnal Upset Stcam line Exa lnlct Reclrc Redrc Normal ~
Upset Ii Upset F ~
Emergency I'mergency S'mergency l
S'ault Fault S Fault S
"~ Design Basis Load Contbinatlon as speclllcd ln reterencc Z3>.Secdon XVIE7 l.
4.5.5.1 The pressure differences for these events arc given in the Table below. Positive direction indicates that the pressure inside of the shroud is higher than that outside of thc shroud, and the prcssure below the core plate is higher than above the core plate.
Component Normal Upset Prcssure Steam Line Recirculation Prcssure (psi) LOCA Pressure Linc LOCA (psi) (psi) Pressure
.(psi)
Shroud Support 21.2 25,6 65.0 -125.0 Core Plate 15.9 18.5 41.0 -182.0 Shroud Head 59 8.9 22.0 7.0 4.5.5.2 A new seismic analysis based on the documents in Paragraph 2.5 shall bc performed, which includes the shroud repair. The shroud repair shall function for thc cntirc continuum from an uncrackcd shroud to a shroud with all horizontal welds (Hl-H8) containing through wall cracks, Therefore, multiple conditions must be'analyzed, for both thc OBE and the DBE
25A5588 sH No. 7 REV. R events, The minimum shroud conditions analyzed are as follows: an uncracked shroud with the installed repair, a shroud with a through wail 360 degree crack at the H8 weld with the installed repair, and a shroud with a through wall 360 degree crack at the HGB weld with the installed repair.
4,8.5.8 Two steady state thermal conditions shall be evaluated, The first is normal operation with the shroud and H8 support brackets at 5SO'F, and the stabilizer assembly at 515'F. The second condition is an upset transient (scram with loss of feedwater pumps) with the shroud and HS support brackets at 422'F, and the stabilizer at 300 F.
4.8.5.4 Asymmetric pressures in the annulus between the shroud and the RPV during the exit recirculation line LOCA event (Emergency 8 and Faulted 3) shall be considered.
4,8,6 ., The minimum safety factors (SFmin) for shroud displacement 4,8,7 vibration,
' 'he (Section 4.2.8) shall be 2.25 for normal and upset, 1.5 for emergency, and 1.125 for faulted.
shroud repair design shall consider potential sources of 4.4 M~~/. ASTM specification niaterial is acceptable for the Shroud Repair. CMTRs are required for all material. Material requirements are contained in the document in Paragraph 2.1 .l.c, 4.5 Zero leakage is not required. The design shall ensure that cracked welds do not separate under normal operating conditions. The desigrt shall account for leakage from the region inside the shroud into the annulus region during normal operation.
4.6 ~i~~
surfaces of Liquid penetrant examination shall be perforined on all final machined all new hardware and on all structural welds per ESOVP22A (Paragraph 2.1.1.a).
4,7 +h..tt;~n The fabrication requirements are contained in the document in Paragraph 2,1.1.c,
- 5. QUALHYASSURANCE 5.1 The shroud repair hardware components are Safety Related as referenced in Paragraph 2,1.2.b. Design, fabrication, installation, and other construction activities shall be controlled per a QA, Program, which satisfies 10CFR50 Appendix B, in order to assure safe and reliable components.