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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20207H7561999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20207H7621999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20236U4751998-07-23023 July 1998 SG Eddy Current Insp Rept Cycle 7 Refueling Outage (B2R07) ML20198J5641998-01-0707 January 1998 Unit 2 Pressure & Temp Limits Rept ML20198J5531998-01-0707 January 1998 Unit 1 Pressure & Temp Limits Rept ML20198J5201998-01-0707 January 1998 Pressure Temp Limits Rept (Ptlr) ML20198J5061998-01-0707 January 1998 Pressure Temp Limits Rept (Ptlr) ML20198P6591997-12-31031 December 1997 .0 Volt IPC Full Cycle Operation Technical Basis Supplement to 'Braidwood Unit 1 Cycle 7 Interim Plugging Criteria Rept,Aug 1997.' ML20199E8801997-11-0303 November 1997 Revised Byron Unit 2 Pressure Temperature Limits Rept (PTLR) ML20199E8751997-11-0303 November 1997 Revised Byron Unit 1 Pressure Temperature Limits Rept (Ptlr) ML20210P8611997-08-31031 August 1997 Cycle 7 Interim Plugging Criteria Rept ML20217G6171997-07-22022 July 1997 Operability Assessment Process Form ML20141K0241997-05-21021 May 1997 Pressure & Temp Limits Rept ML20141K0371997-05-21021 May 1997 Pressure & Temp Limits Rept ML20141K0431997-05-21021 May 1997 Pressure & Temp Limits Rept ML20141K0181997-05-21021 May 1997 Pressure & Temp Limits Rept ML20148P8811997-05-16016 May 1997 Spent Fuel Rack Criticality Analysis Using Soluble B Credit ML20141F7141997-05-15015 May 1997 Operability Assessment Process Form ML20141G6361997-05-15015 May 1997 Interim Plugging Criteria Return to Power Rept ML20138H0001997-04-28028 April 1997 Locked Tube Tts Circumferential Indication Root Cause Determination Evaluation ML20134M3131996-11-13013 November 1996 Revised SG Tube Rupture Analysis for Byron/Braidwood ML20134N3131996-10-31031 October 1996 Sys Design Description for Containment Spray ML20134N8011996-10-31031 October 1996 Spent Fuel Rack Criticality Analysis W/Credit for Soluble Boron ML20129F8921996-09-30030 September 1996 Circumferential Indication Summary Rept ML20129G3881996-08-31031 August 1996 Unit-1 EOC 7B Interim Plugging Criteria Rept ML20116H1461996-08-0101 August 1996 Cycle Length Assessment Rept Addendum ML20113B0951996-06-30030 June 1996 Interim Plugging Criteria Return to Power Rept ML20112B8521996-05-17017 May 1996 Cycle Length Assessment Rept Suppl ML20117J0491996-05-0808 May 1996 At&T Round Cell Nuclear Util User'S Council Charter ML20106G5891996-04-30030 April 1996 Training Dept Braidwood Simulator 1996 Certification Rept ML20101E7651996-03-31031 March 1996 Unit - 1 EOC 7A Interim Plugging Criteria Rept ML20100R7371996-02-29029 February 1996 Cycle 6 Interim Plugging Criteria 90 Day Rept ML20095G0691995-12-31031 December 1995 Interim Plugging Criteria Return to Power Rept ML20094K6101995-11-30030 November 1995 Interim Plugging Criteria Return to Power Rept ML20093G7171995-10-12012 October 1995 Rev 0 to PSA-B-95-18, RELAP5M3 Comparison of Model Boiler 2 MSLB from Hzp Test ML20093G8821995-10-11011 October 1995 Rev 0 to PSA-B-95-17, Calculation of Byron 1/Braidwood 1 D4 SG Tube Support Plate Loads w/RELAP5M3 ML20092A9731995-09-0101 September 1995 Independent Verification of Byron/Braidwood D4 SG Tube Support Plate Differential Pressures During Mslb ML20091M8711995-08-25025 August 1995 Rept of Independent Assessment of Calculation of TSP Forces ML20084V2101995-06-0909 June 1995 Interim Plugging Criteria 90 Day Rept ML20078P1551995-02-0606 February 1995 Probability of Detection by Bobbin Insp ML20078G8351995-01-25025 January 1995 Probability of Detection by Bobbin Insp ML20078F1861995-01-20020 January 1995 Refuel Outage B1R05 RHR HX Nozzles Ultrasonic Indication Summary ML20078G9431995-01-19019 January 1995 EOC 6 Interim Plugging Criteria Rept ML20078R1161994-11-15015 November 1994 Non-proprieatry NFSR-0090, Response to Nuclear Regulatory Staff Request for Addl Info on VIPRE/WRB-2 DNBR Thermal Limit for Westinghouse 17x17 Ofa & Vantage 5 Fuel ML20077N0131994-09-30030 September 1994 Rev 2 Evacuation Time Estimates within Plume Exposure Pathway Emergency Planning Zone for Braidwood Nuclear Generating Station ML20149H1591994-06-30030 June 1994 Spent Fuel Rack Criticality Analysis Considering Boraflex Gaps & Shrinkage ML20106G5961993-06-0202 June 1993 Simulator Malfunction Cause & Effects 1999-09-29
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & ML20217H5221999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Byron Station, Units 1 & 2.With BW990066, Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety BW990056, Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With ML20210R6421999-08-13013 August 1999 ISI Outage Rept for A2R07 ML20210U8111999-08-0404 August 1999 SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With BW990048, Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With ML20210K9861999-07-30030 July 1999 Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20210E2251999-07-21021 July 1999 B1R09 ISI Summary Rept Spring 1999 Outage, 980309-990424 M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function ML20216D3841999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function ML20209G1751999-07-0808 July 1999 SG Eddy Current Insp Rept,Cycle 9 Refueling Outage (B1R09) ML20209H3711999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Byron Station, Units 1 & 2.With BW990038, Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With ML20207H7771999-06-30030 June 1999 Rev 0 to WCAP-15177, Evaluation of Pressurized Thermal Shock for Byron,Unit 2 ML20207H7851999-06-30030 June 1999 Rev 0 to WCAP-15183, Commonwealth Edison Co Byron,Unit 1 Surveillance Program Credibility Evaluation ML20207H7941999-06-30030 June 1999 Rev 0 to WCAP-15180, Commonwealth Edison Co Byron,Unit 2 Surveillance Program Credibility Evaluation ML20207H8071999-06-30030 June 1999 Rev 0 to WCAP-15178, Byron Unit 2 Heatup & Cooldowm Limit Curves for Normal Operations ML20207H7561999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20207H7621999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20195J8001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Byron Station,Units 1 & 2.With BW990029, Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With ML20209H7481999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2 ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML20206R6991999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Byron Station Units 1 & 2.With BW990021, Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With M980023, Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A)1999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) ML20195C7961999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) BW990016, Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205P7001999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Byron Station,Units 1 & 2.With ML20205B5091999-03-26026 March 1999 SER Accepting Relief Requests 12R-24,Rev 0 & 12R-34,Rev 0, Related to Second 10-year Interval Inservice Insp for Byron Station,Units 1 & 2 ML20205C5101999-03-21021 March 1999 Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections ML20204G3831999-03-19019 March 1999 Safety Evaluation Accepting Second 10-yr Interval ISI Request for Relief 12R-11 M990004, Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function1999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function ML20206A8831999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function ML20196A0721999-03-16016 March 1999 Cycle 8 COLR in ITS Format & W(Z) Function 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 ML20207J4371999-03-0808 March 1999 ISI Outage Rept for A1R07 ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations BW990010, Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With ML20204C7671999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Byron Station,Units 1 & 2.With ML20206U9011999-02-15015 February 1999 COLR for Braidwood Unit 2 Cycle 7. Page 1 0f 13 of Incoming Submittal Was Not Included BW990004, Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With1999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with 1999-09-30
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J EVALUATION OF ENERGY ABSORBING MATERIAL FOR PIPE WHIP RESTRAINTS Commonwealth Edison Company Byron and Braidwood Stations, Units 1 and 2 Project Nos. 4391/4392/4683/4684 Nuclear Safety Related SAD File Index No. 8.15.1-9 I
G. C. Kao ,
M. S. Yang i T. Y. Su '
k-Revision 0 - March 1984 Revision 1 - April 1984 i Revision 2 - January 1985 Report No.
SAD-431
- SARGENT&LUNDY ENGINEERS .
8501240141 G50116 PDR ADOCK 05000454 P PDR
SAD-431
,, , Rev. 2 January 1985 Structural Analytical Division Report Issue Summary {,
" Proj ect Byron /Braidwood Number 4391/4392 U* Name 4683/4684 o9 gM Client Commonwealth Edison Company u Report Evaluation of Energy Absorbing Material g, Title for Pipe Whip Restraints I9 f Report Nu=ber SAD-431 Nuclear Safety Related Yes b No O signatures Date Identification of Revisad Pages N &
Prepared by: 4 l /[y./ Revision of E a on pages 2,3 Rev. 2 17 and 18. Deleting 1/14/85 Figure 1 on page 21.
Changing page lii to Revieded by: M ! E#9" iv*
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TABLE OF CONTENTS i J
Section DESCRIPTION PAGE
1.0 INTRODUCTION
SUMMARY
AND CONCLUSIONS 1 1.1 Introduction 1 1.2 Summary 2 13 Conclusions 3
- 20 TEST SPECIMENS 5 3.0 TEST CONDITIONS'AND MEASUREMENTS 7 s t
31 Test Conditions 7 3.2 Measurements 7 i
4.0 TEST EQUIPMENT AND INSTRUMENTATION 9 4.1 Test Equipment 9 42 _ Instrumentation 10 43 Remarks 12 5.0- DATA REDUCTION 14 51 Energy and Displacement 14 52 Energy Absorbed per Unit Volume 16 5.3 Qualification Tests 17 h TABLES 18 FIGURES 21 APPENDIX A - Energy-Displacement Plots Al -
i t.k iv
' ** ' SAD-431 Rev. 2 January 1985 y
fSection 5 describes the procedures used to reduce the ,
/
acquired force data to obtain kinetic energies and displacements o the test specimens. Also, the procedures used to evaluate the " Energy Absorbed per Unit Volume (EAUV)" are also presented. The quantity EAUV is also defined as Ea, where appropriate, in this report. The calculation of E a is documented in SAD Calculation No.
8.15.1-9. Finally, the results of the qualificat.1..n tests are also presented in this section.
The results of the test program are summarized in Section 1.2. .
1.2 Summary A summary of test results is presented in Table 1. This P table presents the values of the essential test parameters in Columns 1 through 4, the measured data in Columns 5 through 7, and the calculated data in Columns 8 and. 9. A summary of test data on EAUV is plotted in Figure 1 j The key findings of the tests may be summarized as follows:
i.
s, The E a in the strong-shear direction at 90 0 impact varies from a minimum of 6.1 IN-KIP /IN3 to a maximum of 7.6 IN-KIP /IN3, ,
1 g
~ '
Rgv. 2 January 1985
- b. The E, in the weak-shear direction at 90 0 impact varies from a minimum of 5 2 IN-KIP /IN3 to a maximum of 7.2 IN- -
KIP /IN 3 ,
- c. The E, in the strong-shear direction at 120 impact is 8.2 IN-KIP /IN3, '
\
- d. The E, in the weak-shear direction at 120 impact is 6.5 ,
IN-KIP /IN3, ,
- e. The E a in the bolted configuration at 90 0 impact is 6.6 IN-KIP /IN 3, l
- f. The test data on 4x4x3 SS were not recorded. However, ,
test data obtained from the remaining EAM specimens are considered adequate to provide information on EAUV. >
Consequently, the missing test record does not have an adverse impact on the test results. *
' t.
1.3 Conclusions i
The conclusions drawn from the results of the EAM test program are as follows: -
\
- a. The average value of E a at 50% strain is 6.2 IN-KIP /IN3 ,
with a range of 5.2 IN-KIP /IN3 to 7.6 IN-KIP /IN3 The corresponding qualification test samples average were 3
i
. - . _ _ _ -- .L
SAD-431
. * *
- R:v. 2 January 1985 The final adjusted values of E a, as shown in Table 1, vary between 5.2 IN-KIP /IN3 to 8.2 IN-KIP /IN3, '
53 Qualfication Tests A total of five qualification tests was performed by HEXCEL to establish EAUV under the normal impact condition. The five specimens were designated as G, H, X, Y and Z. The test conditions and results are summarized in Table 3.
The tests on specimens G and H were performed per Sargent &
Lundy's specification No. FL-2409. Additional tests were performed on specimens X, Y and Z to obtain the information on crush strain.
The values of E a obtained from the qualification tests vary ".
from 5 32 IN-KIP /IN3 to 7.80 IN-KIP /IN 3, c
6 a
17
TABLE 1 c
SUMMARY
.OF TEST PARAMETERS AND RESULTS . .
[
(1) (2) (3) (4) (5) (6) (7) (8 ) * (9) {
TOTAL SALDLE EAM DESIGNATION OF ANVIL DROP DROP IMPACT DIS- CRUSH E*
ULTIMATE ,
TEST SPECIMEN ANGLE WEIGHT HEIGHT VELOCITY PLACEMENT DISTANCE STRAIN IN-KgP/ [
(DEGREE) (LBS . ) (IN) (FPS) (IN) (IN) IN (IN/IN) j 3 x 3 x 3 WS 90 1975 120 25 00 2.90 2.06 5.6 0.67 3 x 3 x 3 SS 90 1975 120 25.03 2.85 2 00 6.1 0.66 ,
4 x 4 x 2 WS 90 1975 120 24 99 1.83 1.27 5.2 0.61 4x4 x 2 SS 90 1975 120 25.02 1 33 0.88 7.6** 0.43 i i
4 x 4 x 2 5/16 WS 120 0 2400 120 25.07 2.13 1.33 6.5 'O.55 4 x 4 x 2 5/16 SS 120 2400 120 25.07 2.13 1.01 8.2** 0.43 i
4 x 4 x 3 WS 90 3050 120 25.08 2.72 1.87 55 0.62 !
$ 4 x 4 x 3 SS 90 3050 120 25 11 2 18 1.77 + 0.58 f
\
4 x 4 x 4 WS 90 4000 120 25.09 3.67 2.57 5.5 0.64 l 4x4 x 4 SS 90 4150 130 26.04 3 52 2.35 6.4 0.58 4 x 4 x 4 BT 90 4150 120 25 09 2.78 2.45 66 0.60 5 x 5 x 4 WS 90 6550 120 25 34 3.74 2.59 5.9 0.65 !
5 x 5 x 4 SS 90 6550 120 25 37 3.23 2.25 6.8 0.56 I
6 x 6 x 3 WS 90 0 6925 120 25.32 2.35 1.54 7.2 0 50 '
6 x 6 x 3 SS 90 6925 120 25 33 2.28 1.47 7.6 0.50 S5$
o<a Legends: * =E a is computed based on 50% strain. @
nww
- = E a is computed based on maximum strain obtained from the test. N "
m
+ = Data Lost m m
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. NN .
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SAD-431- '
soo,- Rav. 2 'i
~ ' , 'i' ' Janur.ry 1985 -
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s FIGURE 1i
SUMMARY
OF:' ENERGY.' ABSORBED PER UNIT VOLUME OF EAM SPECIMENS 4 .- . , , ,
44 e y a
7 21 d