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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
ATTACHMENT8.3 MODIFICATIONDRAWING 107E5679 REV. 7 AND PARTS LIST 107E5679 REV. 5 P,'DR 9608210139 960814 PDR ADQCK 05000220 I
PL107E5679 SI-I NO. 1 GE Nuclear Smyy RF.V. 5 STATUS SHEET DOCUMENT TITI,I'EVISION RFA.CTOR ICE; PARTS LIST FMF: NMP UNIT I)
MPL NO: N/A THIS ITEM ISORCONTAINS A SAFFlY-RFIATFD ITEM YFS g) NO Q EQUIP CMSS CODE
'F.VISION R. MOKI.FR AU~ 0 ~ S~B RA RETRACED WITH CHANGF8 CN05778 CHK BY: T. GI.FOISON PRINTS TO MADE BY APPROVAI 8 GFNERAL EI.FCTRIC COMPANY 175 CURTNFR AYENUF.
R. PASTON 11/18/94 V.W. PFNCE 11/18/94 SAN OSE CAI,IFORNIA95125 CHKD BY: ISSUED T. GI.FOISON 11/18/94 R. AHMANN 11/18/94 CONT ON SHEET 2 hfS WORD (S/28/94) DISK ~ F.Dhf ESS
GE Nuclear Energy SECT REV ITLE: REACTOR General Electric Company, San Jose, California 95125 PL 107E5679 A 05 DESCRIPTION GROUP NUMBER AND QUANTITY ITEM QQCVMcNT DOC NQ. TYPE NAME IDENT IF I CATION STA G001 G002 G003 G004 G005 V/M SRC ACTION 001 ASSEMBLY ASM 11206573GQQl OLT CHANGED 002 ASSEMBLY UPPER SUPPORT 112065746001 OLT CHANGED 003 ASSEMBLY UPPER SPRING OLT DELETED 004 11206575G001 DLT CHANGED 005 ASSEMBLY MIO SUPPO'RT
'112D6576GQ01 OLT CHANGED 006 ASSEMBLY LOWER SUPPORT 007 DETAIL DWG NUT, II E ROD 11206548PQ01 OLT CHANGED OLT Ol. T DELETED 008 OLT DELETED 009 11206588P001 OLT CHANGED 010 DETAIL DWG TQP SUPPORT 11206618G001 OLT CHANGED 013 ASSEMBLY CLAMP/SPACER 050YP5B DLT AR AR AR AR CHANGED 014 YATL SPEC THREAD LUBRICANT 015 ASSEMBLY TIE RQO/SPRING 1 12D6546G001 P I OLT CHANGED ASSEMBLY TIE ROD/SPRING 11206546G002 P I 11206618G002 OLT CHANGED 016 ASSEMBLY CLAMP/SPACER DELETED 017 26281285P001 DLT AR AR AR AR CHANGED 018 DETAIL OWG SPACER 26281285P002 DLT AR AR AR AR CHANGED 019 DETAIL OWG SPACER 26281285P003 DLT AR AR AR AR CHANGED 020 DETAIL OWG SPACER DLT DELETED 021 DLT DELETED 022 OLT DELETED 023 148C69 12P001 CHANGFD 024 DETAIL DWG BOTTOM SPRING SPACER 107E5679GQ02 ADDED 025 ASSEMBLY REACTOR ASM CHANGED ASSEMB1.Y UA'1, CV>I SH YR !!4 DAY $ &f1 NO S'ECT REV EOP 96 08 01 LAST ITEM NO. USED - 028 3 2 PL, 107 E5679 A 05
GENuciear Energy SECT REV TITLE: REACTOR General Electric Company, San Jose, California 95125 PL 107E5679 A 05 DESCR IPTIOM GROUP NUMBER ANO QUANTITY ITEM DOCUMENT DOC E C NAME IDENTIFICATION STA C C G001 G002 0003 G004 G005 U/M SRC ACTION NQ. TYPE 107E5679G003 ADDED 026 ASSEMBLY REACTOR ASM ADDED ASSEMBLY 107E5679G004 ADDED 027 ASSEMBLY REACTOR ASM ADDED ASSEMBLY 107E5679G005 ADDED 028 ASSEMBLY REACTOR ASM ADDED ASSEMBLY DAIS CVYl (W SH VADE OY YR VD DAY SHEET NQ SECT REV EDP 96 08 01 LAST ITEM NO. USED - 028 FINAL SECTION FINAL 3 PL 107E5679 A 05
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Ittt PER VIEW K-K TO PRODUCE .01 MIN AADI U IKK10118
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MEASURE ANNULUS WIDTH. UI AND U2 AT INDICATEO ELEVATIONS.
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MEASURE DISTANCE V AT THE MID SUPPORT. OCOSI 30 276'- PRIOR TO REMOVAL OF THE SHROUD HEAD, SCRIBE DATUM SA-OK Or, 0. CSDCAOCC VIEW SEE SHT B - 90 9 LINE ON VERTICAL SURFACES OF SHROUD AND SHROUD HEA~A SHOWN.
OC03114 AO w
I Ie 2 C-12 0 TORQUE TOGGLE BOLTS TO 40 k5 ft-lbs. TORQUE LOCK NUT TO OK Or. L CLCASOU 96 30%10 FT-LBS. THEN CRIMP THE NUT RETAINER INTO GROOVES OF TOGGLE BOLT. VISUALLY EXAMINE TO CONFIRM THAT CRIMP HAS OCCURED.
THE INDICATED DIMENSION OR REQUIREMENT MAY BE VERIFIED BY Ke-"RE =~ I,"
I3 OF THE INSTALLATION TOOLING AND PROCEDURES IN -'UAUFICATION DCRCD II CC DD @8m MOCK-UP TESTING.
Qt 2S SIZE TOLERANCE OF SLOTS APPLIES AT INSIDE SURFACE 1'HROUD HEAD FLANGE. TO ACCOMOOATE SLOT TAPER, TOLERANCE MAY BE mCIIIC CD*ccR ccc c c INCREASED LINEARLY TO 507> GREATER AT OUTSIDE SURFACE OF SHROUD HEAD FLANGE. Nsv P.vaiiz,b!~ 0>,
1 RRco R* c cc @8m +13 POSTO ND SZE TO BE DEFINED BY CONTROL TOOUNG AND OUALIFIEO'"f PROCESS CONTROL.
- 14. SEPARATE PARTS LIST IDENTIFIED AS PL107E5679.
22 QI Qt THE AS-INSTALLED LOWER CONTACT ON THE LOWER SPRING DOES m<8 8 CC . Rc- cc 166 NOT ENCOMPASS SHROUD WELD H6A. AS WAS INTENDEO BY DESIGN.
Ift I MODIFICATIONS AS SHOWN IN VIEW M WERE MADE TO CAPTURE WELD H6A. lof 1 80' HOLES AT THE 90' 166 AND 270'ZIMUTHS WERE HONED TO 4.11 DIAMETER.
68'ECTION THE UPPER BRACKET ASSEMBLY AT THE 166'ZIMLITH IS NOT CENTERED A A BETWEEN THE SHROUD HEAD BOLT LUGS, IT STRADDLES THE LUGS AS SHOWN IN FDDR EA1 - 0021.
Qt CUSTOMER (NMPC) EPN EQUIPMENT PIECE NUMBER.
PL ISSUED
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Qt Qt 24 TYP FOR AZIMUTHS 90', 17(7 4'5(7 (lt206570P001)
SHOWN IN PHANTOM TYP FOR AZIMUTH L60 Rl04SI
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107E5679 Aq W r I~ 13 10 IC ~ >44I444
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AZIMUTH ITEM - VIEW R AS MEASURED Y EE*Y-.020 +.000 -010 AS MACHINED EE SERIAL ¹ VIEW R 2.03Q 2.011 CORE ao AvaHable on zPC ftUtI'8 CQIt'd SUPPORT 96'76'46'3 13 16 VIEW VIEW R
R 1,969 L797 EERI.949 EERL777 1.948 L776 0 0 16 VIEW R 2.Q5 EER2.105 2.104 O~ VIEW IvI 0 I 0 SR0I TNCKKSS ~ AZIMUTH AZIMUTH ITEM ¹ - VIEW S AS MEASVREO X AS MEASURED Xl X Xl 2.75QS 'ERIAL ¹
- VIEW S 190.766 185.467 2.529 NA 270'0'819.20 166'IL19.20 - VIEW S 190.963 165.500 2.7Q 24 (EE) 270 IIL19.20 - VIEW S 190.281 165.395 2.Q6 NA / (Y) 350'619.20 - VIEW S IBL250 185.405 3.095 NA 8 WELD H6A AZIMUTH ITEM ¹ - DET C AS MEASURED Ul AA<+.261 AS MACH84ED AA SERIAL ¹ \
90'IQD6565) - DET C FDDR EAl-0028 AA~2.786 166'IQD6565) - DET C FDOR EAl-0028 AAR2.155 2.159 270'IQD6565) - DET C FDDR EA1-0028 AA<2.399 2.259 350'IQ06565) - DET C FDDR EAl-0028 AAR2.051 2.055 VIEW R 90'Z ~ I/16 CORE PLATE SPACER ASEEMQ.Y TYP FOR AZIMUTHS 06;%5476'IO 34S 166'Z ~ I/2 AZIMUTH ITEM ¹ - OET GkGI AS MEASURED S AS MEASURED HH 11 ~ .S (S .004-W)-.015~.003 SERIAL ¹ 3517 AZ ~ 5/8 90 (262BQ86)- OET GkGI FDOR EAI 0026 L6710 166'262BQ86)- DET GkGI FODR EA1.0021 0.723 270 (262BQ66)- DET GkGI FDDR EAI 0026 16439 350'262BQ66) OET GkGI FODR EAI 0026 NA VIEW M+s I8 AZIMVTHS 90'. 170; 20 3.768060 +l2 222 I O 350'I2 13 16 (gfoatSa.OI6),
~ SEE NOTE 16 11 12 13 (IQD655NN)
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8 (23<3) 0263)
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-A-
~ 7 6 DETAIL J (L20) SECTION F-F NUT ANO RETAINER (LOWER SUPPORT NOT SHOWN) LOCATION DETAIL G1 lK DETAIL G SHROVD HEAD FLANGE SLOTS AND INSTALLATION UPPER SUPPORT INSTALLED N POSITION ON SHROUD OF STABILIZER SHOWN SEPARATELY FOR CLARITY O AZIMVTHS 90; 170; ,,~
" 107E5679 7 270'50'0 I2 I AC 02MIM
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