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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17241A3541999-06-0101 June 1999 Proposed Tech Specs Section 3.5.2,allowing Up to 7 Days to Restore Inoperable LPSI Train to Operable Status ML17241A3451999-05-24024 May 1999 Proposed Tech Specs 3/4.5.1 Re Safety Injection Tanks ML17229B0711999-03-19019 March 1999 Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit ML17229B0201999-02-23023 February 1999 Proposed Tech Specs 3/4.1.2.9 Re Reactivity Control sys- Boron Dilution ML17229A9551998-12-16016 December 1998 Proposed Tech Specs Pages Revising Administrative Controls & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position ML17229A9161998-11-25025 November 1998 Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases ML17229A9251998-11-22022 November 1998 Proposed Tech Specs Revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1 ML17229A9131998-11-19019 November 1998 Proposed Tech Specs,Revising Administrative Contols TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position ML20155C3061998-10-29029 October 1998 Proposed Tech Specs Pages Revising Terminology Used in Notation of TS Tables 2.2-1 & 3.3-1 Re Implementation & Automatic Removal of Certain Reactor Protection Sys Trip Bypasses ML17229A8441998-08-24024 August 1998 Proposed Tech Specs Removing Obsolete License Conditions & Incorporating Revs Which Clarify Component Operations That Must Be Verified in Response to Containment Sump Recirculation Actuation Signal ML17229A7731998-06-15015 June 1998 Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b ML17229A7601998-06-0303 June 1998 Proposed Marked Up TS Pages Modifying Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 to Provide for Use of Lab Gas Partitioner to Periodically Analyze Concentration of Oxygen in Svc Waste Gas Decay Tank ML17229A7511998-05-27027 May 1998 Proposed Tech Specs Section 6.2.2.f,revised to Allow for Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews ML17229A7481998-05-27027 May 1998 Proposed Tech Specs Section 3.5.1,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions ML17229A7441998-05-27027 May 1998 Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures ML17229A6501998-03-0303 March 1998 Proposed Tech Specs 3.4.7 Re RCS Chemistry/Design Features/ Administrative Controls ML17229A5691997-12-31031 December 1997 Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity ML17309A9131997-12-29029 December 1997 Proposed Tech Specs Modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17229A5491997-12-0101 December 1997 Proposed Tech Specs Revising Units 1 & 2 EPP Section 4, Environ Conditions & Section 5, Administrative Procedures to Incorporate Proposed Terms & Conditions of Incidental Take Statement Included in Biological Opinion ML17229A4621997-08-22022 August 1997 Proposed Tech Specs Pages,Revising Specification 4.0.5 Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Control Section 6.8 ML17229A4341997-08-0101 August 1997 Proposed Tech Specs,Extending semi-annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996 & Associated SE ML17229A3601997-05-29029 May 1997 Proposed Tech Specs Incorporating Administrative Changes That Improve Consistency Throughout TSs & Related Bases ML17229A1831996-12-20020 December 1996 Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings ML17229A1611996-12-0909 December 1996 Proposed Tech Specs 1.9a Re Core Operating Limits Rept ML17229A1191996-10-31031 October 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML17229A1111996-10-30030 October 1996 Proposed Tech Specs 3/4.9.9 Re Containment Isolation Sys & 3/4.9.10 Re Water level-reactor Vessel ML17229A1091996-10-28028 October 1996 Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria ML17229A1061996-10-28028 October 1996 Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel ML17228B5641996-07-15015 July 1996 Revised Tech Specs Re Core Alteration Definition ML17228B5041996-06-0101 June 1996 Proposed Tech Specs Re Thermal Margin & RCS Flow Limits ML17228B3761996-01-0404 January 1996 Proposed Tech Specs Rectifying Discrepancy for Each St Lucie Unit & Providing Assurance That Admin Controls for Hpsip Remain Effective in Lower Operational Modes ML17228B3361995-11-22022 November 1995 Proposed TS 3/4.4.6.1 for RCS Leakage Detection Instrumentation,Adapting STS for C-E Plants (NUREG-1432) Spec 3.4.15 ML17228B2451995-08-16016 August 1995 Proposed TS 3.6.6.1, Sbvs. ML17228B2421995-08-16016 August 1995 Proposed Ts,Reflecting Relocation of Selected TS Requirements Re Instrumentation & Emergency & Security Plan Review Process,Per GL 93-07 ML17228B1891995-06-21021 June 1995 Proposed Tech Specs Re Safety Injection Tank Surveillances ML17228B1811995-06-21021 June 1995 Proposed Tech Specs Re Time Allowed to Restore Inoperable LPSI Train to Operable Status ML17228B1791995-06-21021 June 1995 Proposed Tech Specs Re Extended Allowed Outage Time for EDGs ML17228B1471995-05-17017 May 1995 Proposed Tech Specs,Extending Applicability of Current RCS Pressure/Temp Limits & Maximum Allowed RCS Heatup & Cooldown Rates to 23.6 Effective Full Power Yrs of Operation ML17228B1441995-05-17017 May 1995 Proposed Tech Specs Re Administrative & Conforming Update ML17228B0901995-04-0303 April 1995 Proposed Tech Specs Re Incorporation of line-item TS Improvements to TSs 3/4.8.1 & 4.8.1.2.2 for Licenses DPR-67 & NPF-16 ML17228B0591995-02-27027 February 1995 Proposed TS Re Sdcs Min Flow Rate Requirements ML17228B0521995-02-27027 February 1995 Proposed Tech Spec Tables 3.3-3 & 3.3-4 to Accommodate Improved Coincidence Logic & Relay Replacement for 4.16 Kv Loss of Voltage Relays ML17228B0331995-02-22022 February 1995 Proposed TS 4.6.1.3,reflecting Deletion of Refs to Automatic Tester for Containment Personnel Air Lock ML17228A9921995-01-20020 January 1995 Proposed Tech Specs,Relocating Operability Requirements for Incore Detectors to (TS 3/4.3.3.2) to Updated FSAR & Revising Lhr Surveillance 4.2.1.4 & Special Test Exceptions Surveillance 4.10.2.2,4.10.4.2 & 4.10.5.2 ML17228A9031994-11-0202 November 1994 Proposed Tech Specs 3/4.6.2.1 & 3/4.6.2.3,adapting Combined Spec for Containment Spray & Cooling Sys Contained in Std TS for C-E Plants ML17228A8911994-10-27027 October 1994 Proposed Tech Specs,Incorporating Administrative Changes ML17228A6521994-07-28028 July 1994 Proposed Tech Specs Re LTOP Requirements for Power Operated Relief Valves,Per GL 90-06 ML17228A6591994-07-25025 July 1994 Proposed Tech Specs Implementing Enhancements Recommended by GL 93-05, Line-Item TS Improvements to Reduce SR for Testing During Power Operation. ML17228A6561994-07-25025 July 1994 Proposed Tech Specs for Main Feedwater Line Isolation Valves to Be Consistent w/NUREG-1432,standard TS for C-E Plants ML17228A5771994-05-23023 May 1994 Proposed Tech Specs Removing Option That Allows HPCI Pump 1C to Be Used as Alternative to Preferred Pump for Subsystem Operability 1999-06-01
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17309A9961999-06-30030 June 1999 Rev 35 to HP-90, Emergency Equipment. ML17309A9941999-06-17017 June 1999 Rev 1 to COP-06.06, Guidelines for Collecting Post Accident Samples. ML17241A3541999-06-0101 June 1999 Proposed Tech Specs Section 3.5.2,allowing Up to 7 Days to Restore Inoperable LPSI Train to Operable Status ML17309A9951999-05-27027 May 1999 Rev 0 to COP-06.11, Establishing Remote Lab for Analyses of Accident Samples. ML17241A3451999-05-24024 May 1999 Proposed Tech Specs 3/4.5.1 Re Safety Injection Tanks ML17229B0711999-03-19019 March 1999 Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit ML17229B0441999-03-0202 March 1999 Cycle 11 Reactor Startup Physics Testing Rept. with 990304 Ltr ML17229B0201999-02-23023 February 1999 Proposed Tech Specs 3/4.1.2.9 Re Reactivity Control sys- Boron Dilution ML17229B0361998-12-22022 December 1998 Rev 20 to Procedure C-200, Odcm. ML17229A9551998-12-16016 December 1998 Proposed Tech Specs Pages Revising Administrative Controls & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position ML17229A9161998-11-25025 November 1998 Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases ML17229A9251998-11-22022 November 1998 Proposed Tech Specs Revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1 ML17229A9131998-11-19019 November 1998 Proposed Tech Specs,Revising Administrative Contols TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position ML20155C3061998-10-29029 October 1998 Proposed Tech Specs Pages Revising Terminology Used in Notation of TS Tables 2.2-1 & 3.3-1 Re Implementation & Automatic Removal of Certain Reactor Protection Sys Trip Bypasses ML20153G0781998-08-26026 August 1998 Rev 19 to Plstqp, Guard Training & Qualification Plan ML17229A8441998-08-24024 August 1998 Proposed Tech Specs Removing Obsolete License Conditions & Incorporating Revs Which Clarify Component Operations That Must Be Verified in Response to Containment Sump Recirculation Actuation Signal ML17229A7731998-06-15015 June 1998 Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b ML17229A7601998-06-0303 June 1998 Proposed Marked Up TS Pages Modifying Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 to Provide for Use of Lab Gas Partitioner to Periodically Analyze Concentration of Oxygen in Svc Waste Gas Decay Tank ML17229A7441998-05-27027 May 1998 Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures ML17229A7481998-05-27027 May 1998 Proposed Tech Specs Section 3.5.1,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions ML17229A7511998-05-27027 May 1998 Proposed Tech Specs Section 6.2.2.f,revised to Allow for Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews ML17229A6751998-03-27027 March 1998 Cycle 15 Reactor Startup Physics & Replacement SG Testing Rept. W/980402 Ltr ML17229A6501998-03-0303 March 1998 Proposed Tech Specs 3.4.7 Re RCS Chemistry/Design Features/ Administrative Controls ML17229A6381998-02-12012 February 1998 Rev 19 to C-200, Offsite Dose Calculation Manual. ML17229A6151998-01-12012 January 1998 Rev 0 to ISI-PSL-1, St Lucie Nuclear Plant Unit 1 ISI Plan. ML17229A6141998-01-12012 January 1998 Rev 0 to ISI-PSL-1, Third Interval ISI Program for St Lucie Nuclear Power Plant,Unit 1. ML17229A5691997-12-31031 December 1997 Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity ML17309A9131997-12-29029 December 1997 Proposed Tech Specs Modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17229A5851997-12-12012 December 1997 Rev 0 to ADM-29.01, IST Program for Pumps & Valves. ML17229A5491997-12-0101 December 1997 Proposed Tech Specs Revising Units 1 & 2 EPP Section 4, Environ Conditions & Section 5, Administrative Procedures to Incorporate Proposed Terms & Conditions of Incidental Take Statement Included in Biological Opinion ML17309A9171997-11-26026 November 1997 Rev 0 to PSL-ENG-SENS-97-068, Spent Fuel Pool Dilution Analysis. ML17229A5931997-09-26026 September 1997 Rev 4 to Procedure QI-5-PSL-1, Preparation,Rev,Review/ Approval of Procedures. ML17229A5921997-09-18018 September 1997 Rev 0 to Procedure ADM-17.11, 10CFR500.59 Screening. ML20211Q5841997-09-10010 September 1997 Rev 18 to Training & Qualification Plan ML17229A4621997-08-22022 August 1997 Proposed Tech Specs Pages,Revising Specification 4.0.5 Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Control Section 6.8 ML17229A4341997-08-0101 August 1997 Proposed Tech Specs,Extending semi-annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996 & Associated SE ML17309A8951997-06-11011 June 1997 Rev 0 to PL-CNSI-97-004, Transportation & Emergency Response Plan for St Lucie Unit 1 SG Project. ML17229A3601997-05-29029 May 1997 Proposed Tech Specs Incorporating Administrative Changes That Improve Consistency Throughout TSs & Related Bases ML17229A2981997-03-0606 March 1997 Final Analysis of Radiological Consequences of Main Steam Line Break Outside Containment for St Lucie Unit 1 NPP Using NUREG-0800 Std Review Plan 15.1.5 App A. ML17229A1831996-12-20020 December 1996 Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings ML17229A1611996-12-0909 December 1996 Proposed Tech Specs 1.9a Re Core Operating Limits Rept ML17229A1191996-10-31031 October 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML17229A1111996-10-30030 October 1996 Proposed Tech Specs 3/4.9.9 Re Containment Isolation Sys & 3/4.9.10 Re Water level-reactor Vessel ML17229A1061996-10-28028 October 1996 Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel ML17229A1091996-10-28028 October 1996 Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria ML17229A0951996-10-24024 October 1996 Rev 0 to 00000-OSW-16, In-Situ Pressure Test Results for St Lucie Unit 1 Spring 1996 Outage. ML17229A0861996-10-18018 October 1996 Startup Physics Testing Rept. W/961018 Ltr ML17229A2441996-09-23023 September 1996 Rev 18 to Offsite Dose Calculation Manual (Odcm). ML17228B5641996-07-15015 July 1996 Revised Tech Specs Re Core Alteration Definition ML17229A0961996-06-12012 June 1996 Rev 0 to TR-9419-CSE96-1101, Test Rept - SG Tube In-Situ Hydrostatic Pressure Test Tool Hydro Chamber Pressure Determination. 1999-06-30
[Table view] |
Text
o QQ
- 4) TABLE 8 3 4.4~1 Cont'd
%e UO ClO REACTOR VESSEL TOUGHNESS I AQ m Q4 50 FT-LB/35 HIN. UPPER SHELF UI@
Qs HIL TEMP F RTNDT{4) FT-LB COMP 'ATERIAL CU NI P NDTT
'
>o~ .-F LONG TRANS ONG RAGS M
CONPONENT cue XI@
CODE TYPE lletlet Nozzle )
C-3-1 A508C1.2 F 009 +10 +88 +108 ~48 119 77 Outlet Nozzle , C-3-2 A508C1.2 ~ 010 20 i92 +112 +52 ill 72 Outlet Nozzle Ext. C-17-1 A508C1.2 .013 +20 ,(5) 126 82 Outlet Nozzle Ext. C-17-2 A508C1.2 .013 +20 +28{') 126 82 Upper Shell Plate C-6-3 , A533BCl.l ~ 011 -10 +30 +50 -10 129 84 Upper Shell Plate C-6-2 A533BCl.l .010 -30 +45 +65 +5 123 80 Upper Shell Plate C-6-1 A533BCl.l .012 +10 +42 +62 +10 105 68 Inter. Shell Plate C-7-1 A533BC1.1 O.ll 0.64 0.004 0 .
+26 +46 126 82 Inter. Shell Plate C-7-2 A533BCl.l O.ll 0.64 0.004 -30 +30 +50 -10 131 85 Inter. Shell Plate C-7-3 A533BC1.1 O.ll 0.58 0.004 -30 +50 +70 +10 117 76 Lower Shell Plate C-8-3 A533BC1.1 0;12 0.58 0.004 0 +26 +46 136'8 Lower Shell Plate C-8-1 A533BCl.l 0.15 0.56 0.006 -19 +60 480 +20 126 82
~3 (7)
Lower Shell Plate C-8-2 A533BC1.1 0.15 0.57 0.006 0 +32 +52 20{') 120
~ A ~
O Closure Head Flange C-2 A508C1 ~ 2 .008 +20 +20{5) 143 tb ~
-30
'33 Closure Head Peels C-21-2 A533BCl.l .012 +40 +60 86 Closure Head Peels C-21-2 A533BCl.l .012 -30 +40 +60 133 86
SUMMARY
OF TECHNICAL SPECIFICATION BASES CHANGES NIT 1 PA EB /44-
- 1) Lower shell plate C-8-2: Unirradiated baseline Charpy specimens for this limiting plate were tested as part of the reactor vessel surveillance program. These specimens were oriented in both the longitudinal and transverse direction, thus allowing use of actual test data as opposed to an estimate.
N NIT 1 PA E 4 4-10
- 1) Material type for welds: These changes were made to correct typographical errors that listed the welds as plate. The corrections provide the weld wire heat and flux type for each of the reactor vessel beltline welds.
- 2) Intermediate shell long. welds: These changes provide new estimates of the values of the copper and nickel and are based on a larger body of generic data of CE fabricated submerged arc welds than the previous estimate. The Charpy upper shelf energy value was not previously determined and is based on a large body of generic CE fabricated submerged arc welds fabricated with type 124 flux. The referenced reports which provide the basis for each value is noted.
- 3) Lower shell long. welds: These changes provided new information based on an identical weld (wire heat and flux lot) in the Beaver Valley Unit 1 reactor vessel surveillance program. The new chemistry values are mean values of the chemical analyses from CE during qualification testing, and Westinghouse from the analysis of the Beaver Valley Unit 1 surveillance weld. These are the only know chemical analyses for this weld.
The initial values of NDTT, RT>>Y and upper shelf energy for this weld were obtained from the tests performed as part of the Beaver Valley Unit 1 Surveillance Program with the reference noted.
NIT 2 PA E 4 4-
- 1) Minimum upper shelf Cv energy: this change corrects the upper shelf energy which was mistakenly identified as being tested in the longitudinal direction. The Charpy specimens from the Unit 2 beltline plates were tested in both the longitudinal and transverse (weak) directions. The values reported are actually transverse test data and the table heading is corrected.
TABLE B 3 4.4-5 (.ont'd REACTOR VESSEL TOUGHNESS I
C m 50 FT-LB/35 MIL"TEMP F MIN~ UPPER SHELF COMP MATERIAL CU NI P NDTT RTNDT( ) FT-LS COMPONENT CODE TYPE F LONG TRANS ' P 3)
Closure Head Peels C-21-1 h533BCl.l ~ 013 -10 +20 -10 138 90 Closure Head Peels C-21-1 A533BCl .1 - - .01 3 -10 +20 -10 138 90 Closure Head Peels C-21-2 A533BCl.l - - .012 -30 +40 +60 133 86 Closure Head Peels C-21-3 A533BCl.l .013 -40 +36 +56 129 Closure Head Dome C>>20-1 A533BC1.1 )- ),014 -10 +64 +4 105 68 4 87'/to/3f18009 -
o }'r o(o Inter. Shell Melds Long. 2-203 A,B,C
%5988-Lin~ IQAI AHf%Sf .018 o'"
56(6)
~05)
//02 j (s 3o5 Ikti p.gQ p. C~ ep} (sa Exp Lower Shell Long. 3-203 %888- AHi4'SR I g
()
Melds (roP A,B,C Lf~clc. IO92 gol3(f Lower- to-Inter. 9-203 +5!88- 0.23 0.11 .013 -60 (~) -36(~)
Shell Seam Meld L}gcoo9)
NOTES; (1) Charpy 50 ft-lb and 35 mila lateral expansion index temperature (loner bound)
(2} Oetermined using Branch Technical Position NTEB 5-2, Section 1.1(3)(b)
(3) Determined by using Branch Technical Position MTEB 5-2 Section 1.2 aCL 4) As per ASME BIPV Code,Section III, NB-2331 0 5) Charpy test data either do not have lateral expansion value or the data are not legible...The tt reference temperature from Charpy test data was obtained by following MTEB Position 5.2, Section
~a (6) Estimated based on generic data for C-E submerged arc welds ("Evaluation of Pressurized Thermal 1.1(4)
O Shock Effects due to Small Break LOCABs with Loss of Feedwater for the Combustion Engineering NSSS," CEN-189, December 1981).
(7) Surveillance Program Data - Av~~a>c. LlS E (0) X~iki
-
I g~g P~DPc~>)
g~ g~~~v'sc.cl~>-
<>> ihc~hs<<l C.F-4'- <g 5qg
'.)
J 4. ~ 4)c.<>S C Fah,itc<44 scAh lw i4 Q~auov. V<<nc]
p
(~ad
""
i <4v
'" "" )
tfctllavu. Pc mph'~~ ~
(lo) +~ld C<c~is4~y is > ~<<,7 >+/ f~y~ ( g, alhgly sts a<h ) b4 9
0 4
qE.
1
TABLE 8 3/4.4-1 REACTOR VESSEL TOUGHNESS Hinimum Upper <~5~
Temperature of Shel C e Drop Charpy V-Hotch for 1)
Weight RT ( F) NDT Direc n arpy Piece Ho. Code Ho. Haterial Vessel Location Results 050 ft- lb Ft- lb 122"102A H-604-1 SA 5338 Cl 1 Upper Shel l Plate 0 +50 122-1028 H-604-2 SA 5338 Cl 1 Upper Shell Plate +10 +50 122-102C H"604-3 SA 5338 Cl 1 Upper Shell Plate -10 +10 124"1028 H-605-1 SA 5338 Cl 1 Intermediate Shell 0 +3D 105 Plate 124-102C H-605-2 SA 533B Cl 1 intermediate Shell -10 113 Plate 124-102A H-605-3 SA 5338 Cl 1 Intermediate Shell -20 113 Plate 142-102C H-4116-1 'A 5338 Cl 1 Lower Shell Plate '-30 +20 91 142-1028 H-4116-2 SA 5338 Cl 1 Lower Shell Plate. -50 +20 105 142-102A H-4116-3 SA 5338 Cl 1 Lower Shell Plate -40 +20 )00 102-101 H-4110-1 -SA 5338 Cl 1 Closure Head -lo +30 106-101 H-4101-1 SA 508 Cl 2 Closure Head Flange 0 0 128-101A H-4102-1 SA 508 Cl 2 Inlet Nozzle -20 -20 128-101D H-41D2-2 SA 5DB Cl 2 Inlet Nozzle -20 -20 128-1018 H-4102" 3 SA 508 Cl 2 Inlet Hozzle 0 0
. 128-101C H-4102-4 SA 508 Cl 2 Inlet Nozzle -10 -10 128-3DIB H-4103-1 SA 508 Cl 2 Outlet Nozzle -20 -20 128-301A H-4103-2 SA 508 Cl 2 Outlet Nozzle "30 -30 126-101 H-602-1 SA 508 Cl 2 Vessel Flange -30 -10 131-102A H-4104-1 SA 508 Cl 1 Inlet Hozzle Safe End -20 +20 131-102D H-4104-2 SA 508 Cl 1 Inlet Nozzle Safe End -.20 +20 131-1028 H-4104-3 SA 508 Cl 1 Inlet Nozzle Safe End -20 +2D 131-102C H-4104-4 SA 508 Cl 1 Inlet Hozzle Safe End -20 +20 131-1018 H-4105-1 SA 508 Cl 1 Outlet Nozzle Safe End -10 0 131-101A H-4105-2 SA 508 Cl 1 Outlet Nozzle Safe End -10 0 152-101 H-4112-1 SA 5338 Cl 1 Bottom Head Dome -50 -4D 154-102 H-4111-1 SA 5338 Cl 1 Bottom Head Torus -40 +40 (A to F) 104-102 H-4109-1 SA 5338 Cl 1 Closure Ilead Torus -60 -10
{A to D)
-(1) Repor ted only for be)tline region plates.
0