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{{#Wiki_filter:Page 1 of 1 RULES AND DIRECTIVE, BRANCH U'Nr.C | {{#Wiki_filter:Page 1 of 1 RULES AND DIRECTIVE, S BRANCH U'Nr.C As of: May 17, 2013 Received: May 16, 2013 Status: PendingPost PUBLIC SUBMISSION 21t3 MAY 17 AM 10* Iracking No. ljx-85d2-fqvc Comments Due: May 16, 2013 Submission Type: Web Docket: NRC-201 3-0070 P CFIV f Application and Amendment to Facility Operating License Pnvolvng Prop se o Significant Hazards Consideration Determination Comment On: NRC-2013-0070-0001 Application and Amendment to Facility Operating License Involving Proposed No Significant Hazards Consideration Determination; San Onofre Nuclear Generating Station, Unit 2 Document: NRC-2013-0070-DRAFT-0200 Comment on FR Doc # 2013-08888 4ý ISLU,3 Submitter Information Organization: DAB Safety Team General Comment Charts: San Onofre Unit 2 Modes Of Operation and what that means if a MSLB with Multiple 8 Ruptures occur | ||
May 16, 2013 Status: PendingPost Iracking No. ljx-85d2-fqvc Comments Due: May 16, 2013 Submission Type: Web Docket: NRC-201 3-0070 P CFIV f Application and Amendment to Facility Operating License | @600 gpm to U2 RSGs @0% Power - Radiation will exceed SCE FSAR limits. Offsite releases probability due to multiple tube ruptures will exceed assumed Core Damage Probability (CDP) and Large Early Release Probability (LERP) of 2X 10-7 stated In SCE Enclosure 2, page 20. | ||
NRC-2013-0070-DRAFT-0200 Comment on FR Doc # 2013-08888 4ý ISLU,3 Submitter Information Organization: | Attachments Charts of Unit 2 Submitted SUNSI Review Complete Template = ADM - 013 E-RIDS= ADM-03 Add=. B. Benney (bjb) https ://www.fdms.gov/fdms-web-agency/component/contentstreamer?obj ectld=09000064812e7a65&for... 05/17/2013 | ||
DAB Safety Team General Comment Charts: San Onofre Unit 2 Modes Of Operation and what that means if a MSLB with Multiple 8 Ruptures occur@600 gpm to U2 RSGs @0% Power -Radiation will exceed SCE FSAR limits. Offsite releases probability due to multiple tube ruptures will exceed assumed Core Damage Probability (CDP) and Large Early Release Probability (LERP) of 2X 10-7 stated In SCE Enclosure 2, page 20.Attachments Charts of Unit 2 Submitted SUNSI Review Complete Template = ADM -013 E-RIDS= ADM-03 Add=. B. Benney (bjb)https ://www.fdms.gov/fdms-web-agency/component/contentstreamer?obj ectld=09000064812e7a65&for... | |||
05/17/2013 The DAB Safety Team: February 27, 2013 Media Contact: Don Leichtling (619) 296-9928 or Ace Hoffman (760) 720-7261 Charts: San Onofre Unit 2 Modes Of Operation Table 1 -San Onofre RSGS Design and Operational Data MSLBwith Multiple 8 Design and Operational Ruptures @600 gpm Parameters which caused FEI, U2 RSGs U2 RSGs U2 RSGs FIRVand MFE @100% Power @70% Power @0% Power (1) Reactor Thermal Power, M\ 1729 1215 0 (Reactor Trip)(1A) Unit Electrical Generation, 1183 N/A (2) Number ofTubes 9727 9727 12,580 (3) Average Length of Heated 729.56 729.56 729.56 Tubes, inches m (4) Heat Transfer Area, ft2 116,100 116,100 116,100 (5)Tube Wall Thickness, 0.043 0.043 0.043 inches (5A)Tube Diameter, inches 0.75 0.75 0.75 (5B)Tube Pitch, inches 1.0 1.0 0.87 (5C) Tube Array Triangular Triangular Triangular/Square (5D)TubeIndex 1.33-1.43 1.33-1.43 1.52-1.67 (5 E) Tube to tube clearance, 0.25 0.25 ?inches (5F) Nominal Gap between 0.002 0.002 0.003 tubeand AVB", cold, inches (SG) Nominal Gap between 0 0 0 tube and AVB", Hot, inches (5H) Nominal Gap, N/A N/A N/A Manufacturing Dispersion, inches (51)Tube Wall Thickness/Tube 0.057 0.057 0.057 Diameter Ratio 1 (5J) Average Heated Tube 973 973 973 Length/'Tube Diameter Ratio (6) Reactor Coolant Flow (at 79.8 78.2 0 (RCS Pump Trip)cold leg temperature),, Million lbs./hour (6A) Reactor Coolant 598 591 591 Operating Temperature (Thot), OF (6B) Reactor Coolant 541 551 551 Operating Temperature (Tcold), OF (7) RSG Operating Pressure 892 946 ATM (@100% power), psia (8) Steam Operating 531 538 212 Temperature | The DAB Safety Team: February 27, 2013 Media Contact: Don Leichtling (619) 296-9928 or Ace Hoffman (760) 720-7261 Charts: San Onofre Unit 2 Modes Of Operation Table 1 - San Onofre RSGS Design and Operational Data MSLBwith Multiple 8 Design and Operational Ruptures @600 gpm Parameters which caused FEI, U2 RSGs U2 RSGs U2 RSGs FIRVand MFE @100% Power @70% Power @0% Power (1) Reactor Thermal Power, M\ 1729 1215 0 (Reactor Trip) | ||
(@ 0% power), OF (8A) Steam Flow, Million 7.6 5.1 Feedwater Inventoryto lbs./hour Environment in 5 -15*Minutes-SG Empty (8B) Feed-water Inlet 442 407 N/A Temperature, OF (9) Feedwater Flow, Million 7.6 5.1 0 (Feedwater PumpsTrip) lbs./hour (10) Steam Quality, % 90% 36% >90%(11) Void Fraction, % 98.5% 92.6% 100%(11A) Maximum Gap Fluid 25.1 12.6 >50 Velocity, feet/second (11B)Secondaryfluid 7 12 <7 density, Ibm/cubic feet (12) Reactor Coolant 2003 2003 15,000 gallons RCS Tube Volume, fl3 Inventory contained in tubes escapes to the Environment in 5 -15* Minutes (13) Circulation Ratio 3.3 4.9 0 (13A) Down-comer 24.8 24.8 0 Feed-water Flow, Mlbs./hour (14) Delta Te = (TS, 6A)-(TSAT, 67 53 ~400 7A),OF Fluid Elastic Instability NO NO YES (Film Boiling)2 Significant Radiation** | (1A) Unit Electrical Generation, 1183 N/A (2) Number ofTubes 9727 9727 12,580 (3) Average Length of Heated 729.56 729.56 729.56 Tubes, inches m (4) Heat Transfer Area, ft2 116,100 116,100 116,100 (5)Tube Wall Thickness, 0.043 0.043 0.043 inches (5A)Tube Diameter, inches 0.75 0.75 0.75 (5B)Tube Pitch, inches 1.0 1.0 0.87 (5C) Tube Array Triangular Triangular Triangular/Square (5D)TubeIndex 1.33-1.43 1.33-1.43 1.52-1.67 (5 E) Tube to tube clearance, 0.25 0.25 ? | ||
Flow-induced Random YES YES YES Vibration Mitsubishi Flowering Effect YES NO YES Flashing FeedwaterJet N/A N/A YES Impingement Forces on Tubes Compilation of data based on Publicly Available Documents (e.g., Westinghouse Operational Assessment, SCE Unit 3 Root cause Evaluation, http://wwv.efunda.com/materials/water/steamtablc sat.cti, etc.)* No Operator Action assumed in 15 minutes** Radiation will exceed SCE FSAR limits. Offsite releases probability due to multiple tube ruptures will exceed assumed Core Damage Probability (CDP) and Large Early Release Probability (LERP) of2X 10-7 stated In SCE | inches (5F) Nominal Gap between 0.002 0.002 0.003 tubeand AVB", cold, inches (SG) Nominal Gap between 0 0 0 tube and AVB", Hot, inches (5H) Nominal Gap, N/A N/A N/A Manufacturing Dispersion, inches (51)Tube Wall Thickness/Tube 0.057 0.057 0.057 Diameter Ratio 1 | ||
.. ..._ _ _ _ _ 4-- | |||
(5J) Average Heated Tube 973 973 973 Length/'Tube Diameter Ratio (6) Reactor Coolant Flow (at 79.8 78.2 0 (RCS Pump Trip) cold leg temperature),, | |||
Million lbs./hour (6A) Reactor Coolant 598 591 591 Operating Temperature (Thot), OF (6B) Reactor Coolant 541 551 551 Operating Temperature (Tcold), OF (7) RSG Operating Pressure 892 946 ATM | |||
(@100% power), psia (8) Steam Operating 531 538 212 Temperature (@ 0% power), | |||
OF (8A) Steam Flow, Million 7.6 5.1 Feedwater Inventoryto lbs./hour Environment in 5 -15* | |||
Minutes-SG Empty (8B) Feed-water Inlet 442 407 N/A Temperature, OF (9) Feedwater Flow, Million 7.6 5.1 0 (Feedwater PumpsTrip) lbs./hour (10) Steam Quality, % 90% 36% >90% | |||
(11) Void Fraction, % 98.5% 92.6% 100% | |||
(11A) Maximum Gap Fluid 25.1 12.6 >50 Velocity, feet/second (11B)Secondaryfluid 7 12 <7 density, Ibm/cubic feet (12) Reactor Coolant 2003 2003 15,000 gallons RCS Tube Volume, fl3 Inventory contained in tubes escapes to the Environment in 5 -15* Minutes (13) Circulation Ratio 3.3 4.9 0 (13A) Down-comer 24.8 24.8 0 Feed-water Flow, Mlbs./hour (14) Delta Te = (TS, 6A)-(TSAT, 67 53 ~400 7A),OF Fluid Elastic Instability NO NO YES (Film Boiling) 2 | |||
Significant Radiation** | |||
Flow-induced Random YES YES YES Vibration Mitsubishi Flowering Effect YES NO YES Flashing FeedwaterJet N/A N/A YES Impingement Forces on Tubes Compilation of data based on Publicly Available Documents (e.g., Westinghouse Operational Assessment, SCE Unit 3 Root cause Evaluation, http://wwv.efunda.com/materials/water/steamtablc sat.cti, etc.) | |||
* No Operator Action assumed in 15 minutes | |||
** Radiation will exceed SCE FSAR limits. Offsite releases probability due to multiple tube ruptures will exceed assumed Core Damage Probability (CDP) and Large Early Release Probability (LERP) of2X 10-7 stated In SCE , page 20. | |||
3 | |||
Boiling Regimes Free Convection Nucleate Transition Film | |||
.. ... _ _ _ _ _ 4-- *W-Radiation effects significant- 4 Isolated st'able Jets and F.llm Bubbles Columns so )lllng 104 | |||
: 101, 5 10 30 120 1000 ATe = Ts- Ta (oC) | |||
Boiling Curve for water at I atm. | |||
Surface heat flux q" as a function of excess temperature ATe= Ts-T littp://en.wikipedia.org/wiki/Film boiling 4 | |||
1.5 1.0 - | |||
0.5 01 0 1.0 2.0 3.0 PITCH FLOW VELOCITY lm/sl Figure 1 - Vibrations amplitude as a function of flow pitch velocity for a flexible cylinder In a rigid cluster (taken from Pettigrew et al. 1991). The cylinder Is free to vibration in the cross-flow direction. | |||
==Reference:== | ==Reference:== | ||
YJqkC. R., Pettigrew, M.I., NtVXS N.W. (2006). fl1q4jl4l Instability of an Array of Tubes Preferentially Flexible in the Flow Direction Subjected to Two-Phase Cross Flow._Zmnmds.k. | |||
YJqkC. R., Pettigrew, M.I., NtVXS N.W. (2006). fl1q4jl4l Instability of an Array of Tubes Preferentially Flexible in the Flow Direction Subjected to Two-Phase Cross Flow. _Zmnmds.k. | efL4(ASF, Journalof Pressure Vessel Technology, 128(1), p. 148-159. | ||
efL4(ASF, | These charts will be posted on the web at this link: DAB Safety Team Documents. | ||
The DAB Safety Team: Don, Ace and a BATTERY of safety-conscious San Onofre insiders plus industry experts from around the world who wish to remain anonymous. | The DAB Safety Team: Don, Ace and a BATTERY of safety-conscious San Onofre insiders plus industry experts from around the world who wish to remain anonymous. These volunteers assist the DAB Safety Team by sharing knowledge, opinions and insight but are not responsible for the contents of the DAB Safety Team's reports. We continue to work together as a Safety Team to prepare additional: DAB Safety Team Documents, which explain in detail why a SONGS restart is unsafe at any power level without a Full/Thorough/Transparent NRC 50.90 License Amendment and Evidentiary Public Hearings. For more information from The DAB Safety Team, please visit the link above. | ||
These volunteers assist the DAB Safety Team by sharing knowledge, opinions and insight but are not responsible for the contents of the DAB Safety Team's reports. We continue to work together as a Safety Team to prepare additional: | Our Mission: To prevent a Trillion Dollar Eco-Disaster like Fukushima, from happening in the USA. | ||
DAB Safety Team Documents, which explain in detail why a SONGS restart is unsafe at any power level without a Full/Thorough/Transparent NRC 50.90 License Amendment and Evidentiary Public Hearings. | Copyright February 27, 2013 by The DAB Safety Team. All rights reserved. This material may not be published, broadcast or redistributed without crediting the DAB Safety Team. The contents cannot be altered without the Written Permission of the DAB Safety Team Leader and/or the DAB Safety Team's Attorney. | ||
For more information from The DAB Safety Team, please visit the link above.Our Mission: To prevent a Trillion Dollar Eco-Disaster like Fukushima, from happening in the USA.Copyright February 27, 2013 by The DAB Safety Team. All rights reserved. | 5}} | ||
This material may not be published, broadcast or redistributed without crediting the DAB Safety Team. The contents cannot be altered without the Written Permission of the DAB Safety Team Leader and/or the DAB Safety Team's Attorney.5}} | |||
Revision as of 18:41, 4 November 2019
| ML13143A476 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/16/2013 |
| From: | - No Known Affiliation |
| To: | Rules, Announcements, and Directives Branch |
| References | |
| 78FR22576 00292, NRC-201 3-0070 | |
| Download: ML13143A476 (6) | |
Text
Page 1 of 1 RULES AND DIRECTIVE, S BRANCH U'Nr.C As of: May 17, 2013 Received: May 16, 2013 Status: PendingPost PUBLIC SUBMISSION 21t3 MAY 17 AM 10* Iracking No. ljx-85d2-fqvc Comments Due: May 16, 2013 Submission Type: Web Docket: NRC-201 3-0070 P CFIV f Application and Amendment to Facility Operating License Pnvolvng Prop se o Significant Hazards Consideration Determination Comment On: NRC-2013-0070-0001 Application and Amendment to Facility Operating License Involving Proposed No Significant Hazards Consideration Determination; San Onofre Nuclear Generating Station, Unit 2 Document: NRC-2013-0070-DRAFT-0200 Comment on FR Doc # 2013-08888 4ý ISLU,3 Submitter Information Organization: DAB Safety Team General Comment Charts: San Onofre Unit 2 Modes Of Operation and what that means if a MSLB with Multiple 8 Ruptures occur
@600 gpm to U2 RSGs @0% Power - Radiation will exceed SCE FSAR limits. Offsite releases probability due to multiple tube ruptures will exceed assumed Core Damage Probability (CDP) and Large Early Release Probability (LERP) of 2X 10-7 stated In SCE Enclosure 2, page 20.
Attachments Charts of Unit 2 Submitted SUNSI Review Complete Template = ADM - 013 E-RIDS= ADM-03 Add=. B. Benney (bjb) https ://www.fdms.gov/fdms-web-agency/component/contentstreamer?obj ectld=09000064812e7a65&for... 05/17/2013
The DAB Safety Team: February 27, 2013 Media Contact: Don Leichtling (619) 296-9928 or Ace Hoffman (760) 720-7261 Charts: San Onofre Unit 2 Modes Of Operation Table 1 - San Onofre RSGS Design and Operational Data MSLBwith Multiple 8 Design and Operational Ruptures @600 gpm Parameters which caused FEI, U2 RSGs U2 RSGs U2 RSGs FIRVand MFE @100% Power @70% Power @0% Power (1) Reactor Thermal Power, M\ 1729 1215 0 (Reactor Trip)
(1A) Unit Electrical Generation, 1183 N/A (2) Number ofTubes 9727 9727 12,580 (3) Average Length of Heated 729.56 729.56 729.56 Tubes, inches m (4) Heat Transfer Area, ft2 116,100 116,100 116,100 (5)Tube Wall Thickness, 0.043 0.043 0.043 inches (5A)Tube Diameter, inches 0.75 0.75 0.75 (5B)Tube Pitch, inches 1.0 1.0 0.87 (5C) Tube Array Triangular Triangular Triangular/Square (5D)TubeIndex 1.33-1.43 1.33-1.43 1.52-1.67 (5 E) Tube to tube clearance, 0.25 0.25 ?
inches (5F) Nominal Gap between 0.002 0.002 0.003 tubeand AVB", cold, inches (SG) Nominal Gap between 0 0 0 tube and AVB", Hot, inches (5H) Nominal Gap, N/A N/A N/A Manufacturing Dispersion, inches (51)Tube Wall Thickness/Tube 0.057 0.057 0.057 Diameter Ratio 1
(5J) Average Heated Tube 973 973 973 Length/'Tube Diameter Ratio (6) Reactor Coolant Flow (at 79.8 78.2 0 (RCS Pump Trip) cold leg temperature),,
Million lbs./hour (6A) Reactor Coolant 598 591 591 Operating Temperature (Thot), OF (6B) Reactor Coolant 541 551 551 Operating Temperature (Tcold), OF (7) RSG Operating Pressure 892 946 ATM
(@100% power), psia (8) Steam Operating 531 538 212 Temperature (@ 0% power),
OF (8A) Steam Flow, Million 7.6 5.1 Feedwater Inventoryto lbs./hour Environment in 5 -15*
Minutes-SG Empty (8B) Feed-water Inlet 442 407 N/A Temperature, OF (9) Feedwater Flow, Million 7.6 5.1 0 (Feedwater PumpsTrip) lbs./hour (10) Steam Quality, % 90% 36% >90%
(11) Void Fraction, % 98.5% 92.6% 100%
(11A) Maximum Gap Fluid 25.1 12.6 >50 Velocity, feet/second (11B)Secondaryfluid 7 12 <7 density, Ibm/cubic feet (12) Reactor Coolant 2003 2003 15,000 gallons RCS Tube Volume, fl3 Inventory contained in tubes escapes to the Environment in 5 -15* Minutes (13) Circulation Ratio 3.3 4.9 0 (13A) Down-comer 24.8 24.8 0 Feed-water Flow, Mlbs./hour (14) Delta Te = (TS, 6A)-(TSAT, 67 53 ~400 7A),OF Fluid Elastic Instability NO NO YES (Film Boiling) 2
Significant Radiation**
Flow-induced Random YES YES YES Vibration Mitsubishi Flowering Effect YES NO YES Flashing FeedwaterJet N/A N/A YES Impingement Forces on Tubes Compilation of data based on Publicly Available Documents (e.g., Westinghouse Operational Assessment, SCE Unit 3 Root cause Evaluation, http://wwv.efunda.com/materials/water/steamtablc sat.cti, etc.)
- No Operator Action assumed in 15 minutes
3
Boiling Regimes Free Convection Nucleate Transition Film
.. ... _ _ _ _ _ 4-- *W-Radiation effects significant- 4 Isolated st'able Jets and F.llm Bubbles Columns so )lllng 104
- 101, 5 10 30 120 1000 ATe = Ts- Ta (oC)
Boiling Curve for water at I atm.
Surface heat flux q" as a function of excess temperature ATe= Ts-T littp://en.wikipedia.org/wiki/Film boiling 4
1.5 1.0 -
0.5 01 0 1.0 2.0 3.0 PITCH FLOW VELOCITY lm/sl Figure 1 - Vibrations amplitude as a function of flow pitch velocity for a flexible cylinder In a rigid cluster (taken from Pettigrew et al. 1991). The cylinder Is free to vibration in the cross-flow direction.
Reference:
YJqkC. R., Pettigrew, M.I., NtVXS N.W. (2006). fl1q4jl4l Instability of an Array of Tubes Preferentially Flexible in the Flow Direction Subjected to Two-Phase Cross Flow._Zmnmds.k.
efL4(ASF, Journalof Pressure Vessel Technology, 128(1), p. 148-159.
These charts will be posted on the web at this link: DAB Safety Team Documents.
The DAB Safety Team: Don, Ace and a BATTERY of safety-conscious San Onofre insiders plus industry experts from around the world who wish to remain anonymous. These volunteers assist the DAB Safety Team by sharing knowledge, opinions and insight but are not responsible for the contents of the DAB Safety Team's reports. We continue to work together as a Safety Team to prepare additional: DAB Safety Team Documents, which explain in detail why a SONGS restart is unsafe at any power level without a Full/Thorough/Transparent NRC 50.90 License Amendment and Evidentiary Public Hearings. For more information from The DAB Safety Team, please visit the link above.
Our Mission: To prevent a Trillion Dollar Eco-Disaster like Fukushima, from happening in the USA.
Copyright February 27, 2013 by The DAB Safety Team. All rights reserved. This material may not be published, broadcast or redistributed without crediting the DAB Safety Team. The contents cannot be altered without the Written Permission of the DAB Safety Team Leader and/or the DAB Safety Team's Attorney.
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