Package Consisting of Request for Addl Info Re Alternative Pipe Break Criteria Attached to NRC to Util| ML20214K274 |
| Person / Time |
|---|
| Site: |
South Texas  |
|---|
| Issue date: |
07/10/1986 |
|---|
| From: |
NRC |
|---|
| To: |
|
|---|
| Shared Package |
|---|
| ML20214K217 |
List: |
|---|
| References |
|---|
| FOIA-86-784 NUDOCS 8612020245 |
| Download: ML20214K274 (3) |
|
|
|---|
Category:ARCHIVE RECORDS
MONTHYEARIA-97-252, Packages Consisting of 19 Pages of Accession Numbers for South Texas Project1997-10-0707 October 1997
Packages Consisting of 19 Pages of Accession Numbers for South Texas Project
ML20217F7671997-10-0707 October 1997
Packages Consisting of 19 Pages of Accession Numbers for South Texas Project
ML20115E7131996-02-13013 February 1996
Rev 2 to Sub-Calculation MC-6441-101, Pressure Locking/ Thermal Binding Evaluation
ML20198J5581995-06-0606 June 1995
Rev 0 to MC-6458, ECCS Isolation Valve Leak Analysis. W/ One Oversize Drawing
ML20198J5521995-06-0606 June 1995
Rev 1 to MC-6313, ECCS Valve Leakage to RWST Analysis
ML20059H3951993-11-0101 November 1993
Cold Ecw Chiller Analysis
ML20058J5591993-10-14014 October 1993
Essential Chilled Water Load
ML20059H3751993-10-0505 October 1993
Essential Chilled Water Load
ML20059H3611993-09-28028 September 1993
Essential Chiller Performance Test
ML20046A1421993-03-19019 March 1993
Package Consisting of 1993 Emergency Response Graded Exercise Objectives
ML20092C7681992-01-0909 January 1992
Package Consisting of Objectives for 1992 Graded Emergency Preparedness Exercise on 920429
ML20197B1461991-11-20020 November 1991
Rev 1 to Calculation MC-6305, RHR Relief Valves as Coms/Ltop
ML20079N3791991-11-11011 November 1991
Response to NUMARC Survey in Support of NRC License Renewal Rulemaking
ML20055J4631990-05-0909 May 1990
Package Consisting of Director Highlights of Unusual Event Due to Required Shutdown by Tech Spec 3.4.6.1 for Pressure Boundary Leakage.Unit Entered Cold Shutdown to Make Repairs. Estimated Restart Date Is 900522
ML20055H8791990-05-0808 May 1990
Package of Info Re 900508 Shutdown Due to Pressure Boundary Leakage
ML20247R3711989-09-18018 September 1989
Package of Three FOIA Requests
ML20246P8441989-05-0505 May 1989
Errata to Annotated Rev to FSAR & Tech Specs Bases
ST-HL-AE-3040, Proposed Revs to FSAR1989-04-18018 April 1989
Proposed Revs to FSAR
ML20148C5971988-03-18018 March 1988
Slide Prsentation Entitled, Commission Briefing on Full Power Licensing of South Texas Project,Unit 1
ML20237D7901987-12-10010 December 1987
Package of Unrelated Documentation Re Listed Plants Concerning NRC Emergency Response Data Sys
HL-3708, Record of 870819 Telcon W/A Singh,P Kadambi of Nrc,A Guidry of Bechtel Re Deviations Not Documented in Plant Ser.Nrc Concurred That Deviations Described in Attachment 2 to ST-HL-AE-2252 Acceptable1987-08-19019 August 1987
Record of 870819 Telcon W/A Singh,P Kadambi of Nrc,A Guidry of Bechtel Re Deviations Not Documented in Plant Ser.Nrc Concurred That Deviations Described in Attachment 2 to ST-HL-AE-2252 Acceptable
HL-7514, Record of Telcon W/Ca Ayala,Ma Friedlander,Rl Perch,R Emch & C Moon on 870708 to Clarify Intent & Proper Interpretation of Encl marked-up Final Draft Tech Spec Table 3.3-31987-07-0808 July 1987
Record of Telcon W/Ca Ayala,Ma Friedlander,Rl Perch,R Emch & C Moon on 870708 to Clarify Intent & Proper Interpretation of Encl marked-up Final Draft Tech Spec Table 3.3-3
ML20209F5901987-03-13013 March 1987
Region IV Daily Rept on 870311 Steam/Water Hammer Event at Facility & Photographs of Facility Piping
ML20209B0091987-02-0202 February 1987
Package of Supplemental Info Re Reg Guide 1.75 Testing Configurations
ML20212G6831987-01-16016 January 1987
Package of Comments on Facility long-term Cooling Analysis
ML20207N3951987-01-12012 January 1987
Package of Three Pages Providing Addl Clarification of Instrument Tubing
ML20214A1831986-10-15015 October 1986
Nonproprietary Version of Slide Presentation Entitled, Presentation & Handout Matl Re Leak-Before-Break Calculations for South Texas Project 12-Inch Diameter Accumulator Line
ML20211F0041986-09-30030 September 1986
Marked-up Notice of Violation from Insp on 791110-800207, Draft Investigation Rept & Proposed Enforcement Actions
IA-86-784, Package Consisting of Request for Addl Info Re Alternative Pipe Break Criteria Attached to NRC to Util1986-07-10010 July 1986
Package Consisting of Request for Addl Info Re Alternative Pipe Break Criteria Attached to NRC to Util
ML20214K2741986-07-10010 July 1986
Package Consisting of Request for Addl Info Re Alternative Pipe Break Criteria Attached to NRC to Util
ML20207E1021986-07-0202 July 1986
Telcon W/Util,Nrc & Westinghouse to Discuss Bart Code Assessment
ML20207F6921986-07-0202 July 1986
Telcon W/Sl Wu & P Kadambi of NRC to Discuss Util Providing Supplemental Info on Momentary Fuel Assembly Liftoff,Per SER Confirmatory Item 9
HL-3578, Record of 860630 Telcon W/R Goel & P Kadambi of NRC Re NRC Review of Fire Hazards/Safe Shutdown.Summary of Changes Incorporated Into Amend 4 to Fire Hazards Analysis Rept Encl1986-06-30030 June 1986
Record of 860630 Telcon W/R Goel & P Kadambi of NRC Re NRC Review of Fire Hazards/Safe Shutdown.Summary of Changes Incorporated Into Amend 4 to Fire Hazards Analysis Rept Encl
HL-3576, Record of Telcon W/Mr Wisenburg,Pg Trudel,T Roberson,R Goel & P Kadambi Re NRC Review of Fire Hazards Analysis Rept & Safe Shutdown1986-06-25025 June 1986
Record of Telcon W/Mr Wisenburg,Pg Trudel,T Roberson,R Goel & P Kadambi Re NRC Review of Fire Hazards Analysis Rept & Safe Shutdown
ML20199G0611986-06-18018 June 1986
Record of 860618 Telcon W/Nrc,Util,Bechtel & Westinghouse Re Deletion of Sump Additive Tank from Facility Design
ML20204A0251986-04-22022 April 1986
Record of 860422 Telcon W/J Brammer,S Hou,S Long, T Robertson,M Powell,W Watson & P Kadambi Re Pipe Break Screening Criteria.Jet Load Calculations Will Not Be Performed w/NUREG/CR-2913 Methodology
ML20207P2701986-01-14014 January 1986
Supplemental Info Received on Safe Shutdown Issue
ML20010D9081981-08-26026 August 1981
Slide Presentation Re Soil Structure Interaction
ML19350E1901981-05-26026 May 1981
Slide Presentation from 810526 Meeting Re Hafnium Control Rods
1997-10-07
[Table view]
Category:PACKAGE OF NONCODED MATERIAL
MONTHYEARML20217F7671997-10-0707 October 1997
Packages Consisting of 19 Pages of Accession Numbers for South Texas Project
IA-97-252, Packages Consisting of 19 Pages of Accession Numbers for South Texas Project1997-10-0707 October 1997
Packages Consisting of 19 Pages of Accession Numbers for South Texas Project
ML20046A1421993-03-19019 March 1993
Package Consisting of 1993 Emergency Response Graded Exercise Objectives
ML20092C7681992-01-0909 January 1992
Package Consisting of Objectives for 1992 Graded Emergency Preparedness Exercise on 920429
ML20079N3791991-11-11011 November 1991
Response to NUMARC Survey in Support of NRC License Renewal Rulemaking
ML20055J4631990-05-0909 May 1990
Package Consisting of Director Highlights of Unusual Event Due to Required Shutdown by Tech Spec 3.4.6.1 for Pressure Boundary Leakage.Unit Entered Cold Shutdown to Make Repairs. Estimated Restart Date Is 900522
ML20055H8791990-05-0808 May 1990
Package of Info Re 900508 Shutdown Due to Pressure Boundary Leakage
ML20247R3711989-09-18018 September 1989
Package of Three FOIA Requests
ML20246P8441989-05-0505 May 1989
Errata to Annotated Rev to FSAR & Tech Specs Bases
ST-HL-AE-3040, Proposed Revs to FSAR1989-04-18018 April 1989
Proposed Revs to FSAR
ML20237D7901987-12-10010 December 1987
Package of Unrelated Documentation Re Listed Plants Concerning NRC Emergency Response Data Sys
ML20209F5901987-03-13013 March 1987
Region IV Daily Rept on 870311 Steam/Water Hammer Event at Facility & Photographs of Facility Piping
ML20209B0091987-02-0202 February 1987
Package of Supplemental Info Re Reg Guide 1.75 Testing Configurations
ML20212G6831987-01-16016 January 1987
Package of Comments on Facility long-term Cooling Analysis
ML20207N3951987-01-12012 January 1987
Package of Three Pages Providing Addl Clarification of Instrument Tubing
ML20211F0041986-09-30030 September 1986
Marked-up Notice of Violation from Insp on 791110-800207, Draft Investigation Rept & Proposed Enforcement Actions
ML20214K2741986-07-10010 July 1986
Package Consisting of Request for Addl Info Re Alternative Pipe Break Criteria Attached to NRC to Util
IA-86-784, Package Consisting of Request for Addl Info Re Alternative Pipe Break Criteria Attached to NRC to Util1986-07-10010 July 1986
Package Consisting of Request for Addl Info Re Alternative Pipe Break Criteria Attached to NRC to Util
ML20207P2701986-01-14014 January 1986
Supplemental Info Received on Safe Shutdown Issue
1997-10-07
[Table view] |
Text
. -- . . -.
o 2Gjoof to D
i ATTAC,HMENT REQUESTFORADDITI'h,iALINFORMATION
- 1. Material Characterization a) For the base and weld metal actually in the South Texas surge line provide the mechanical properties (e.g. ultimate and yield strengths) or other significant material property, which will characterize the mate' rial.
1 b) Indicate the type of weld and post weld heat treatment used to fabricate the welds in the surge line.
c) Provide a materials evaluation to demonstrate that the material stress-strain curve, Jic, and J-R curve used in the analyses are representative of the material in the surge line. This evaluation should follow the general guidelines in NUREG-1061, Vol. 3, and include a comparison, of the material properties for the surge line to the material properties for test data.
- 2. History of Cracking 4
Section 2.0 of WCAP 10489 should include references to NUREG-0691 and
- NUREG 0531 reports. Evaluate the susceptibility of the surge line to j stress corrosion cracking that is described in these NUREG's.
- 3. Loads l$d20goyj5861124 GRABER86-784 PDR 4
a) List individual axial loads and bending moment components used to determine the resultant axial forces and bending moments indicated on page 3-2 of WCAP 10489.
b) Provide a qualitative discussion of why a circumferential flaw in l
a straight pipe section is more limiting than a longitudinal flaw in an elbow or other component.
% 1~2.@'2.4 1 6
/.
-2
- 4. Stability Analysis ..
a)
How were loads combined to d fermine the crack opening area in the leak rate calculation? Provide justification that the method of combining loads is conservative, b)
The stability analysis should meet the margins on load and flaw size in Sections 5.2 (h) and (i) and factor of 10 on leakage discussed in Section 5.7 of NUREG 1061 Vol. 3.
c)
The bilinear stress strain curve is a nonconservative representation of the data points shown in Figure 5-11 of WCAP 10489.
Provide justification that these curves conservatively ,
represent the surge line material described in item 1.
d)
Describe the method of validating (bench marking) each computer code used in the leak rate and fracture mechanics calculations.
- 5. Leak Rate Analysis The crack opening area used in the leak rate computation is the average of the opening area obtained from displacements at the pipe inner and outer surfaces.
more appropriate. It seems that the minimum area would be Provide justification for using the average value.
- 6. Fatigue Crack Growth Analysis a)
The data cited in Reference 8-2 as the basis for the fatigue crack growth rate should be included in the report in graphical form that would illustrate and justify the fatigue crack growth rate constants in equation 8-4 of WCAP 10489. These equations should represent the fatique crack growth rate of the material characterized in item 1.
4 1
)d, ,
df b) The applicant will perform s realistic analysis as possible using service level A and B loads. The aspect ratio for the postulated crack in the fatigue evaluation should be 6. The aspect ratio should remain constant throughout the analysis.
Unless otherwise justified the maximum allowable flaw depth is the smaller of:
. (1) 60% of the wall' thickness, or (2) the depth at which the plastic zone is equal to the remaining ligament.
c) The length of the fatique crack must be less than both:
3 (1) the length of the instability thru-wall crack at J2 (N+SSE) and (2) 1/2 (instability thru-wall flaw at N+SSE)
The applicant is requested to confirm that the fatigue analysis includes the items listed in b) and c), above.
i 1
,,--e - , - - - - _ - - - , , - -. - , - - - - - - - - , , , - - - -