|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211Q4981999-09-10010 September 1999 Proposed Tech Specs Clarifying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits & Adding Ref to Caldon TR for LEFM ML20211G3221999-08-26026 August 1999 Proposed Tech Specs 4.0.6 Re SG Surveillance Requirements ML20212H0771999-08-20020 August 1999 Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820. Page 119 in Unit 1 ASME Section XI of Incoming Submittal Not Included ML20212G0821999-08-20020 August 1999 Rev 4 to Augmented Inservice Insp Plan for Cpses,Unit 1 ML20210R7091999-08-13013 August 1999 Revised Proposed Tech Specs for LAR 98-010,proposing Rev to TS Table 3.3.1-1, RT Sys Instrumentation & TS Table B 3.3.1-1, RT Sys Setpoints ML20211M0041999-08-0505 August 1999 Rev 31 to Technical Requirements Manual ML20211G7401999-07-27027 July 1999 Revs 29 & 30 to Technical Requirements Manual (TRM) for Cpses,Units 1 & 2 ML20209E1861999-07-0909 July 1999 Proposed Tech Specs,Adding Reactor Core Safety Limit Figures to Section 5.6.5 of Ts,Clarifying That Overpower N-16 Setpoint Remains in TS & Reflecting NRC Approval of TRs Used to Determine Core Operating Limits Presented in COLR ML20212J4251999-06-23023 June 1999 Proposed Tech Specs,Revising EDG Start Be Emergency Start Instead of Normal Start Following Loss of Offsite Power ML20195E5401999-06-0404 June 1999 Proposed Tech Specs Pages 3.2-6,3.4-24,3.4-25,3.7-23,3.7-30, 3.8-25,3.9-9,3.9-10 & 4.0-2,provided as Addl Aditorial Changes Supplementing LAR 99-001 ML20195B6461999-05-27027 May 1999 Marked-up TS Pages Re LAR 99-004,changing Plant Battery Surveillance ML20195B6771999-05-24024 May 1999 Proposed Tech Specs Relocating Parameter Limits Allows for Available Operating & Analytical Margins to Be Used in Most Efficient Manner ML20206G7111999-05-0404 May 1999 Proposed Tech Specs Revising Surveillances Associated with Plant Battery & EDGs & Miscellaneous Editorial Corrections ML20206Q0311999-04-16016 April 1999 Rev 28 to CPSES Technical Requirements Manual ML20205Q1681999-04-14014 April 1999 Rev 27 to CPSES Technical Requirements Manual ML20207F3511999-02-25025 February 1999 Fire Endurance Test to Qualify Protective Envelope for Class IE Electrical Circuits ML20203B0011999-01-25025 January 1999 Rev 10 to Security Training & Qualification Plan ML20211C1071999-01-15015 January 1999 Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval ML20198J3171998-12-21021 December 1998 Proposed Tech Specs,Proposing Changes Administratively for Unit 1 & Increasing Licensed Power for Operation of Unit 2 to 3445 Mwt ML20198J2541998-12-18018 December 1998 Proposed Tech Specs Sections 1.0,3.1,3.3,3.4,3.6,3.7,3.9 & 5.0,converting to ITS ML20198J5211998-12-17017 December 1998 Corrected Tech Specs Pages for Section 3.8 to 971211 Submittal Re TS Conversion Application ML20197K0491998-12-11011 December 1998 Proposed Tech Specs Section 3.8, Electrical Power Systems, Converting to ITS ML20196C5361998-11-20020 November 1998 Proposed TS Converting to ITS Sections 4.0,3.4 & 3.6 ML20195F1751998-11-13013 November 1998 Proposed Tech Specs,Revising Administrative Controls Section to Include Configuration Risk Mgt Program Into CPSES TS ML20195F5291998-11-11011 November 1998 Proposed Tech Specs Revising Core Safety Limit Curves & Overtemperature N-16 Reactor Trip Setpoints for Unit 2 Cycle 5 ML20196B8811998-10-30030 October 1998 Proposed Tech Specs Section 3.3 Re Instrumentation ML20154R7861998-10-21021 October 1998 Proposed Tech Specs Section 3.7, Plant Systems ML20154S2901998-10-14014 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Control,Respectively ML20154C9101998-10-0202 October 1998 Proposed Tech Specs 4.0.6, SG SR, Adding Definitions Required for F* Alternate Plugging Criterion & Identifies Portion of Tube Subject to Criteria ML20153E2661998-09-24024 September 1998 Proposed Improved Tech Specs Sections 3.4, RCS & 5.0, Administrative Controls ML20237E8461998-08-28028 August 1998 Proposed Tech Specs Pages Re Sections 1.0,2.0 & 3.0 of Proposed TS Changes in 980707 & s,In Response to NRC RAI ML20154C4511998-07-20020 July 1998 Interim Change Request ISI-1R5-01, Unit 1 ISI Plan,Rev 5 ML20236T9931998-07-20020 July 1998 1RF06 ISI Summary Rept First Interval,Third Period,First Outage for CPSES Unit 1, Commerical Operating Date 900830 ML20236J3131998-07-0101 July 1998 Revised Proposed Tech Specs Pages Re Safety Injection Signal & Blackout Signal ML20249C6101998-06-22022 June 1998 Proposed Tech Specs Section 3.6 Re Conversion Application ML20216B2811998-04-24024 April 1998 Rev 13 to Cpses,Units 1 & 2,IST Plan for Pumps & Valves First Interval ML20216E6291998-04-0909 April 1998 Marked-up TS Pages,Reflecting Proposed Changes in Amends to Licenses NPF-87 & NPF-89 ML20216B1471998-04-0606 April 1998 Proposed Tech Specs,Allowing Plant to Continue to Operate W/O Having to Perform Portions of SRs ML20217A3901998-03-18018 March 1998 Proposed Tech Specs Surveillance Requirements 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a) at Power Re Enforcement Discretion ML20216H1361998-03-13013 March 1998 Proposed Tech Specs Re Electrical Systems Surveillance Requirements ML20248L3191998-03-12012 March 1998 Proposed Tech Specs TS 4.8.1.1.2f.4)b) & TS 4.8.1.1.2f.6)b) Re Request for Enforcement Discretion ML20216D6021998-03-0909 March 1998 Proposed Tech Specs Temporarily Removing Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of SRs 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a),for Unit 2 Only ML20203K8621998-02-27027 February 1998 Proposed Tech Specs,Increasing RWST low-low Level Setpoint ML20203J5211998-02-25025 February 1998 Proposed Tech Specs Page to Remove Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of Surveillance Requirements 4.8.1.1.2f.4(a) & 4.8.1.1.2f.7(a) Until Plant Startup Subsequent to Next Refueling Outage ML20203J6151998-02-24024 February 1998 Rev 26 to Technical Requirements Manual ML20217P1531998-02-12012 February 1998 Rev 2 to ISI-2R2-01, Unit 2 ISI Plan ML20202B1641998-02-0505 February 1998 Proposed Tech Specs Bases 3/4.7.1.5 Re Main Steam Line Isolation Valves ML20217P2961998-01-30030 January 1998 Rev 5 to Unit 1 ISI Program Plan ML20202E5981997-11-25025 November 1997 Rev 12 to CPSES Units 1 & 2 IST Testing Plan for Pumps & Valves,First Interval ML20212C3881997-10-24024 October 1997 Proposed Tech Specs Re Revised Core Safety Limit Curves & Revised Overtemperature N-16 Reactor Trip Setpoints 1999-09-10
[Table view] Category:TEST REPORT
MONTHYEARML20207F3511999-02-25025 February 1999 Fire Endurance Test to Qualify Protective Envelope for Class IE Electrical Circuits ML20112G4061996-05-30030 May 1996 CPSES Unit 2 Cycle 3 Startup Rept ML20067D2151994-01-14014 January 1994 First Periodic Reactor Containment Bldg Integrated Leakage Rate Test Final Rept, for Comanche Peak Ses Unit 1 ML20059F5341993-10-0404 October 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (Flex-Blanket Wrapped Cables Laid in 36 Inch Cable Tray Assembly) ML20059F5281993-10-0404 October 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (Box Design Air Drop from Two Nested 24 Inch Cable Tray Assemblies) ML20059F5231993-08-27027 August 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (24 Inch Cable Tray Assembly W/2 Inch Diameter & 1-1/2 Inch Diameter Air Drop) ML20059F5041993-08-27027 August 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (Three 24 Inch Cable Tray Assemblies) ML20059F5111993-08-23023 August 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (12 Inch Cable Tray & 2 Inch Conduit) ML20036C5281993-04-20020 April 1993 Electrical Test to Determine Ampacity Derating of Protective Envelope for Class 1E Electrical Circuits ML20036C5171993-03-19019 March 1993 Fire Endurance Test to Qualify Protective Envelopes for Class 1E Electrical Circuits ML20128H1191993-01-14014 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (24 Inch Tray W/Air Drops) ML20128H1121993-01-13013 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (24 Inch Tray W/Tee) ML20128G9981993-01-13013 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (12 Inch Tray) ML20128H0181993-01-13013 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (30 Inch Tray W/Tee) ML20128H0521993-01-13013 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (3/4 Inch,1-1/2 Inch & 2 Inch Conduits) ML20128H0771993-01-13013 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (30 Inch Tray) ML20128H0311993-01-11011 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (Two 3 Inch Conduits W/Junction Boxes) ML20128H1021993-01-0707 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (Two 3 Inch Conduits W/Junction Boxes) ML20128H0921993-01-0505 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (3/4 Inch,3 Inch & 5 Inch Conduits W/Radial Bends) ML20128H0681992-11-0404 November 1992 Fire Endurance Test of Thermolag 330-1 Fire Protective Envelope (36 Inch Tray W/Tee) ML20126C8361992-09-30030 September 1992 Reactor Containment Building Integrated Leakage Rate Test for Comanche Peak Steam Electric Station,Unit 2 Final Rept ML20044B5591992-04-29029 April 1992 Toxicological Evaluation of Combustion Products from Thermal Barrier Matl Decomposed Under Flaming & Nonflaming Conditions, Rept of Test Fr 3987 ML20062D8951990-11-12012 November 1990 Cycle 1 Startup Rept TXX-9008, Cycle 1 Startup Physics Tests Control Rod Worth Predictions Utilizing TU Electric Control Rod Swap Methodology1990-03-23023 March 1990 Cycle 1 Startup Physics Tests Control Rod Worth Predictions Utilizing TU Electric Control Rod Swap Methodology ML19327A9401989-07-31031 July 1989 Final Rept, Reactor Containment Bldg Integrated Leakage Rate Test ML20235J4461989-01-11011 January 1989 Rev 1 to Test Rept Demonstration of IE to Non-IE Isolation for RS-232C Serial Data Port ML20151E4691988-07-13013 July 1988 Civil/Structural Tests Re Hilti Expansion Anchors Installed in Coredrilled Holes & Richmond Inserts W/Partial Bolt Engagements ML20155J8071988-03-31031 March 1988 Final Summary Rept Comanche Peak Conduit Tests, Technical Rept ML20235F9041987-09-11011 September 1987 Rev 3 to M-28, Justification of Clip Modelling Procedure ML20235F8551987-07-27027 July 1987 Rev 2 to M-38, Siderail Extension Study ML20235F7881987-07-23023 July 1987 Rev 3 to M-12, Qualification Procedures for Cable Tray Support Evaluation ML20235F8201987-05-0505 May 1987 Rev 2 to M-27, Thermal Load Evaluation ML20210C8031987-02-28028 February 1987 Rev 0 to Comanche Peak Steam Electric Station Cable Tray Sys Analysis/Test Correlation ML20210C8911987-02-25025 February 1987 Rev 1 to Thermal Load Evaluation ML20210D2441987-02-24024 February 1987 Vol 1 to Book 25, Reduced Section Properties for Channels ML20210D1351987-02-17017 February 1987 Vol 1 of Book 24 to Cth Post-Test Analysis Correlation ML20210D1651987-01-31031 January 1987 Rev 0 to Comanche Peak Cable Tray Tests, Final Summary Rept ML20236N4161986-10-0909 October 1986 Rev 3 to LIS-100C, Min Required Gap Between Bldgs ML20236N4681986-10-0909 October 1986 LIS-501C, Turbine Bldg Seismic Displacement ML20236N4331986-10-0101 October 1986 Rev 4 to LIS-100C, Min Required Gap Between Secondary Walls & Floors Above ML20211K1801986-09-19019 September 1986 Rev 1 to Calculation/Problem ROTC-06, Multimode Factor Evaluation Train C ML20236N4861986-09-0505 September 1986 LIS-520C, Relative Displacement Between Reactor & Auxiliary Bldgs at Elevation 916 Ft ML20236N4611986-09-0505 September 1986 Rev 0 to LIS-100C, Min Required Gap Between Rcb & Auxiliary Bldg at Approx 900 Ft & Above ML20212D6211986-09-0404 September 1986 Test Rept 48422-1, Cable Separation Test Program ML20211K1871986-07-10010 July 1986 Test Rept for Static Testing of Train C Beam Clamps & Unistrut Hangers for Comanche Peak Steam Electric Station (Cpses) ML20211K2151986-05-27027 May 1986 Rev 0 to Calculation/Problem ROTC-02, Procedure to Calculate Anchor Bolt Loads,Train C Conduit 2 Inches & Under ML20212D7021986-05-0101 May 1986 Test Rept 48037-02, Electrical Raceway Separation Verification Testing ML20236N4501985-11-11011 November 1985 LIS-100C, Min Required Gap Between Containment Wall & Internal Structure A07596, Torsiograph Test of Emergency Diesel Generator 1DG2 at Comanche Peak Steam Electric Station1985-02-28028 February 1985 Torsiograph Test of Emergency Diesel Generator 1DG2 at Comanche Peak Steam Electric Station ML20107A9731984-12-31031 December 1984 Reactor Containment Bldg Unit 1 Preoperational Type B & C Local Leak Rate Test 1999-02-25
[Table view] |
Text
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PRESENTATION TO US NUCLEAR REGULATORY COMMISSION JULY 13, 1988 COMANCHE PEAK STEAM ELECTRIC STATION UNTT 1 AND COMMON
~
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CIVIL / STRUCTURAL TESTS CONCERNING HILTI EXPANSION ANCHORS INSTALLED IN COREDRILLED HOLES AND RICHMOND INSERTS WITH PARTIAL BOLT ENGAGEMENTS
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STONE & WEBSTER ENGINEERING CORPORATION 8807260081 880715
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13306-18051-B2 1
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Tests of Hilti Kwik-Bolts in Coredrilled Holes Issue (Cygna RIL No. 7)
Coredrilled holes may be slightly larger in diameter than holes drilled with Hilti masonry carbide bits, resulting in a potential reduction in pullout capacity.
Resolution A testing program has been completed by SWEC to - validate the pullout capacity of Hilti anchors installed in coredrilled holes.
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Tests of Hilti Kwik-Bolts in Coredrilled Holes '(Cont.)
Test Program Test slab poured using CPSES 4,000 psi concrete as specified in Specification 2323-CS-9, Revision 6.
Hilti expansion anchors were installed in test slab per Specification 2323-SS-30, Revision 3.
Tension tests were performed per ASTM E-488.
Specimens 3/4 in. Hilti Kwik Bolts 1 in. Hilti Kwik Bolts 1 in. Hilti Super Kwik Bolts 1 1/4 in. Hilti Kwik Bolts Test results were adjusted downward to account for actual c,oncrete compressive strength of 5230 psi.
Test report is No.
18051.01-CS(B)-17-09, "Report on Tes,ts of Hilti Kwik-Bolts in Coredrilled Holes".
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TEST CAPACITY AS 7.
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SIZE (in)
DEPTH (in)
TYPE TYPE CAPACITY CAPACITY Of DESIGN CAPACITY REMARKS 3/4" 9"
H M
5.875 3.131 53 NOTABLE I
3/4" 9"
H D-5.875 2.160 37 REDUCilON 3/4" 8"
H M
5.750 3.875 67 NOTABLE 3/4" 8"
H D
5.750 2.967 52 REDUCliON
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5.250 5.681 108 COMPARABLE. APPROACH 3/4" 7"
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5.250 5.052 96 DESIGN CAPACITY i
1" 10" H
M 5.860 7.920 135 EXCEEDS DESIGN
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1" 10" H
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12.439 11.474 92 1-1/4" 10-1/2" H
M 10.225 10.102 99 COMPARABLE 1-1/4" 10-1/2" H
D 10.225 9.861 96 Notes j
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M = Mosonary bit (Monufactured by Hitti) control condition
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Design capacities are from DBD-CS-015 ond include o factor of safety of 4.
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3/4 in. Anchors with 8 in, and 9 in. Embedments Notable reduction DBD-CS-015 will be revised Existing installations will be addressed Reported to NRC - Letter No. TXX-88533 e
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4 Tests of Richmond Inserts with Partial Bolt Engagements Issue In certain instances, bolts were determined to be installed in Richmond inserts with short thread engagements.
Resolution A testing program was performed to determine the capacities of Richmond inserts with a range of bolt engagements and load combinations. The results of the tests were incorporated into the Design Basis Document DBD-CS-015.
Installations that utilized Richmond inserts have been design validated based on the design criteria specified in the Design Basis Document.
Test Program Tests were performed on unused, in-plant, 1-in. and 1 1/2-in. Richmond inserts.
Shear, tension, and shear / tension interaction tests were performed for.
a range of bolt engagements.
Tests were performed in accordance with ASTM E-488, as applicable.
13306-18051-B2 5
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e Tests of Richmond Inserts with Partial Bolt Engagements (Cont.)
Two test serie:
General population of Richmond inserts tested.
1-in. inserts tested using "turn-of-the-nut installation method to simulate early HVAC installations.
Test Reports 16345/6-CS(B)-17-05, "Report on Tests of Richmond Inserts with l
Partial Bolt / Rod Thread Engagement".
16345/6-CS(B)-17-06, "Report on Preliminary Tests of Richmond Inserts with Pretensioned High Strength Bolts and Partial Bolt Engagement".
16345/6-CS(B)-17-07, "Report on Final Qualification Tests of Richmond Inserts with Pretensioned High Strength Bolts and Partial Bolt Engagement".
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1 INCH, TYPE EC-2W RICHMOND INSERT, SA-193, 3/4" ENCAGE 1ENT 40,000 I
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36,000 T4 10208 LBS. TD4SICN TEST ADJLSTED j ULI'INATE IDAD - TABLE 5 Sa : 33,584 GS. SHEAR TEST ADJUSTED L*LITMATE IDAD (AVERAGE)-TABLE 3 32,000 i
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la==*dlaccur=v l Act=t l a=wd.d IAccur=y l Actet i tw,. lin.ut lnecoredlAccur=y l Actu.t li,.ut l l
l l
l Lad la *cti=l Lad I toad la=*ct i=l Lad l ltailur=l tad la**cti=l tad Iratturej 4
l l
l l..______l...______l..._____l__________l______.__l.......l.....__.l_______l.______l......___l........l.......l j
l l(inch) l(inch) l( M )l(p anh) l(pass)l (W) l( M ) l(p ens)l(ft Itm)l (Y/u) l(pens)l(poes) l(pomh)l (Y/u) l
]
l__....__g...__..l...____l........l____.....l........l..........l__..__...l.....___l.....___l__.....l.......l........l.....___l....._.l lTu-os l ria l o.9ao l 2500l
-ic7l 2193l 30300l
-141sl 2anasl600(*) l mo l m/A l N/A l m/A l N/A l 4
lru-o2 l ria io.a9sl iam l
-asl tri6l stam l - nas i sosis i m/A - l u.
I m/A l m/A l m/A i m/A l q
i ru-os l 7/a l o.916 l 3000l
_i4ol za6ai 2itool 9es l 2atis i m/A - l mo i m/A l N/A l wiA l m/A l lTu-os l 7/a i o.am l 1900l
-a9l istil zorm l
-967l 19733 l m/A-l uo l N/A -I m/A l m/A l m/A l l Tu-os l 7/a l o.a46 l 2900l
-13sl 276s'l 1o100l
-472 l 9628l m/A*l Yes l m/A l m/A l m/A l m/A l lTu-o6 l 7/a l o.917 l 4000l
-ta7l 313l 22800l -1o65l 21735 l < aoo l No l m/A l m/A l N/A l m/A l 1
l ru-or i i_us l i.277 l 4000l
_i4 l 3as9l 4s600l
-i6to l 43990 l < 750 l u.
l 3o639l
-769l 29erol res l
]
l Tu-os l i-i/4 l i.2e9 l 33m l
-116l 31a41 45am l.i u6 l 422 a l < m l u.
I m39 l
-769l 29siol res l lru-o9 li-i/4li.zasl 36m l
.iz7l 3473l 49100l
.ir33 l 47367 l < 700 l u.
l 35494l
-a91 l 34603 l res l j
l ru io li-v4l3.266l 36m l
.iz7l 3473l 459m l
_is79l 4o42 l < 6so l mo l 30639l
-769l 29siol ve. l J
lTu-it l i-i/4 l i_277 l 4tm l
-34sl 39n i siom l
_iam i 4920e l < 6so l u.
l 3o639l
-769l 29ero i ve. l l
l l
l 1
l 1
I l
l l
l l
l l
l i
q
.i
- Dial type torgae urench not eval!abte, no torgae vetue recorded.
i l
1 q
l t
a Tests of Richmond Inserts with Partial Bolt Engagements (Cont.)
For 1-in.
bolts pretensioned by the turn-of-the-nut method full design loads can be applied when engagement is 1 5/16 in. (62%) or greater.
For this population, design allowable loads are:
Normal load - 4000 lb (FS=3)
Ext. rems-load - 6000 lb (FS=2)
~_.
O W
e 13306-18051-B2 7
......,,,....,...._.,,,,c-
.__t
July 15, 1988 a-Sumary of July 13, 1988 Audit 1-5/16-inch, the capacity of the insert was reduced and the turn-of-the-nut method of pretensioning bolts resulted in damage to the insert.
A total of 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> was involved in this audit.
(originalsignedby)
David Terao, Project Manager Comanche Peak Project Division Office of Special Projects
Enclosures:
1.
List of Audit Participants 2.
Presentation to NRC Staff cc: See next page
,,, DISTRIBUTION,,,,?
k, Docket F11e-NRC PDR local PDR CPPD Reading OSP Reading JPartlow CGrimes PMcKee JHWilson JLyons RWarnick Hialloy D1 trao CPPD-LA OGC-WF FMiraglia EJordan BGrimes ACRS(10)
LShao GBagchi JMa BLiaw JFair CPPD:0SP AD:CPPD:0SP DTerao:cm JHWil o 07//f/88 07/is /
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