Thermal-Hydraulic Phenomena/Future Plant Designs - February 15, 2002
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
COMBINED THERMAL-HYDRAULIC PHENOMENA/FUTURE PLANT DESIGNS:
SUBCOMMITTEE MEETING:
ANO-2/CLINTON POWER STATION CORE POWER UPRATE REQUESTS
AP1000 PHASE 2 ADVANCED PLANT DESIGN REVIEW
FEBRUARY 13-15, 2002
ROCKVILLE, MARYLAND
PRESENTATION SCHEDULE
| Contact: | P. Boehnert (301/415-8065) (pab2@nrc.gov) A. Singh (415-6899) (axs@nrc.gov) M. El-Zeftawy (415-6889) (mme@nrc.gov) |
February 13, 2002
| TOPIC | PRESENTER | TIME | ||
|---|---|---|---|---|
| I. | Opening Remarks | G. Wallis, Chairman | 8:30 a.m. | |
| II. | Arkansas Nuclear One, Unit 2 Power Uprate | |||
| A. Entergy Presentations (Closed as Necessary) | Entergy | 8:35 a.m. | ||
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| - Include Discussion of Necessary Modifications to Plant Operating Parameters/Plant Hardware (e.g. BAM tank, RV Fluence & P-T Limits) | ||||
| 3. Compliance with Regulatory Requirements | ||||
| -Analyses Performed - Impact on Plant Margins |
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| 4. Review Issues: | ||||
| - Plant Operator Training/Impact on Operator Action Times - ATWS Event Response for Uprate Conditions - Fuel response for ATWS/Power Excursions - Material Degradation Issues (e.g., Alloy 600/FAC) - SG Tube Integrity - Impact on Containment Response/P,T Limits - Piping Stress Limits - Inspection Program |
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| 5. ECCS Analyses | ||||
| - Results | ||||
| 6. Resolution of Open Issues | ||||
| - Radiological Analyses for Control Room, SGTR and LOCA | ||||
| 7. PRA Analyses | ||||
| - Analyses Performed/Results (CDF/LERF, CDFs & LERFs, Associated Uncertainties) - Evaluation of Other PRA Elements (e.g., fire, seismic, shutdown risk) |
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| 8. Concluding Remarks | ||||
| ***LUNCH*** | 12:00 p.m. | |||
| B. NRR Presentations (Open) | NRR | 1:00 p.m. | ||
| 1. Introduction | ||||
| - Scope of SE | ||||
| 2. Reactor Systems Review 3. Plant Systems Review 4. Mechanical & Civil Engineering Review (including RSGs, NSSS & BOP Piping) 5. Materials & Chemical Engineering Review (including SG tube integrity, CEDMs, RV Fluence/PT Limits, Alloy 600 Program) 6. Resolution of Open Issues (addressed in Radiological Analyses Review) 7. PRA Analyses/Evaluation Of Licensee's PRA Examinations 8. Concluding Remarks |
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| C. Subcommittee Caucus (Open) | 2:30 p.m. | |||
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| III. | Recess | 2:45 p.m. | ||
| IV. | Clinton Power Station, Unit 1 Extended Power Uprate | |||
| A. Opening Remarks | G. Wallis, Chairman, | 3:00 p.m. | ||
| B. AmerGen Presentations (Closed as Necessary) |
Amergen/GENE | 3:15 p.m. | ||
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| - Hardware Modifications - Analyses Performed - Exceptions To ELTR1/ 2 Requirements - Impact on Plant Margins |
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| 4. Review Issues: | ||||
| - Plant Operator Training/ Operator Action Times - Stability Monitor/ Instability Avoidance - ATWS Event Rsponse for Uprate Conditions - Fuel response for ATWS/Power Excursions - Material Degradation Issues (e.g.,IASCC/FAC) - Impact on Containment Response/Load Limits - Piping Stress Limits - Inspection Program - Impact of Uprate on Steam Separator/Dryer System |
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| V. | Recess | 6:00 p.m. | ||
February 14, 2002
| VI. | Reconvene | G. Wallis, Chairman | 8:30 a.m. | |
| VII. | Clinton Uprate (Cont.) | |||
| B. AmerGen Presentations (Cont.) (Closed as Necessary) |
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| 5. ECCS Analyses | AmerGen | 8:40 a.m. | ||
| - Results | ||||
| 6. PRA Analyses | ||||
| - Analyses Performed/ Results (CDF/LERF, CDFs & LERFs, Associated Uncertainties(1)) - Evaluation of Other PRA Elements(2) (e.g., fire, seismic, shutdown risk) |
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| 7. Concluding Remarks | 10:00a.m. | |||
| C. NRR Presentations (Open) | NRR | 10:15 a.m. | ||
| 1. Introduction | ||||
| - Staff Evaluation - Comments on SER Quality Upgrade |
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| 2. Reactor Systems Review 3. Plant Systems Review 4. Response to ACRS Questions |
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| - Review of Exceptions to ELTR1&2 - Material Degradation Issues - PRA Analyses/Evaluation Of Licensee's PRA Examinations - Human Performance |
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| 5. Concluding Remarks | ||||
| D. Subcommittee Caucus (Open) | 11:45 a.m. | |||
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| VIII. | Recess | 12:00 p.m. | ||
| IX. | AP1000 Phase 2 Pre-Application Review | |||
| A. Introduction | T. Kress, ACRS | 1:00 p.m. | ||
| B. NRC Overview | A. Drozd, NRR | 1:05 p.m. | ||
| C. Design Acceptance Criteria & Exemptions | ||||
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A. Drozd J. Wilson, NRR D. Terao/G. Bagchi, NRR W Representative |
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| ***BREAK*** | 3:00 p.m. | |||
| D. Staff Position on Codes/Testing | A. Drozd | 3:15 p.m. | ||
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S. Bajorek W Representative |
3:25 p.m. 4:30 p.m. 4:45 p.m. |
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| X. | Recess | 5:00 p.m. | ||
February 15, 2002
| XI. | Reconvene | T. Kress | 8:30 a.m. | |
| D. Staff Position on Codes/Testing (Cont.) | ||||
| 4. Applicability of AP600 Codes | ||||
| - Reactor Codes - Westinghouse Response |
W. Jensen, NRR W Representative |
8:35 a.m. 9:40 a.m. |
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| ***BREAK*** | 10:15 a.m. | |||
| - WGOTHIC Containment Code - Westinghouse Response |
E. Throm W Representative |
10:30 a.m. 11:00 a.m. |
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| E. Subcommittee Caucus (Open) | 11:30 a.m. | |||
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| XII. | Adjourn | 11:45 a.m. | ||
1. If uncertainty evaluations not performed, provide a qualitative discussion of this matter.
2. If quantitative analyses not available, provide rigorous qualitative arguments.
Page Last Reviewed/Updated Monday, July 13, 2020
Page Last Reviewed/Updated Monday, July 13, 2020