ML11178A068

Meeting Slides, Turkey Point Nuclear Plant, Units 3 and 4, Extended Power Uprate (Epu), NRC and FPL Public Meeting

ML11178A068
Person / Time
Site:	Turkey Point
Issue date:	06/23/2011
From:	Florida Power & Light Co
To:	Jason Paige Plant Licensing Branch II
Shared Package
ML11195A170	List: ML11178A067 ML11178A068 ML11195A152
References
TAC ME4907, TAC ME4908
Download: ML11178A068 (21)

Text

Agenda

• Opening

• Purpose

• EPU License Amendment Request (LAR) Review Summary

• Proposed Technical Specification Changes

• Mechanical and Civil Outstanding Questions

• Nuclear Performance and Code Review

- Boron Precipitation Analysis Discussion

• Containment and Ventilation EPITOME Analysis

• Reactor Systems Branch Questions

• Questions

• Closing 2 -I=PL.

Turkey Point -- Opening

• Appreciate the Staff's support and participation today

• Significant progress made to date

• FPL seeks clarification and understanding of remaining Staff questions

• Encourage open and active dialogue to address open items from the Staff's review 3 -a=pL.

Turkey Point -- Purpose

• Review status of Requests for Additional Information (RAls)

• Discuss remaining questions and/or open items

• Discuss "to go" plan for final draft safety evaluation (SE) to Advisory Committee on Reactor Safeguards (ACRS) 4 8 I=PL.

EPU LAR Review Summary

• 6 draft SEs are complete for the 17 branches

• 4 draft SEs are in branch concurrence

• Draft Environmental Assessment scheduled for 7/15/1

• Focus today is to resolve any questions and/or open items remaining

- Technical Specifications - Confirm no questions or comments on proposed Technical Specifications

- Mechanical and Civil Engineering - Follow-up questions

- Nuclear Performance and Code - PHOENIX-P/ANC benchmarking and boron precipitation

- Containment and Ventilation - EPITOME issue

- Reactor Systems - outstanding RAls and RETRAN deck 5 -F=PL,

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Mechanical and Civil Engineering

• Received 6 follow-up RAls on 6/20/11

- Spent Fuel Pool Cooling and Component Cooling Water modification design information

- Normal containment cooler modification design information

- Containment penetration anchor margins

- Use of actual material properties for reactor vessel supports

- Allowable stresses for control rod drive mechanisms

- Steam Generator fluid steam mixture velocity information

• Clarification discussion today

• Preparing responses with a target of mid July 2011 7 - I=PL.

Nuclear Performance and Code Review

• Providing additional information regarding PHOENIX-PlANe benchmarking - Target early July

• Boric Acid Precipitation

- Status of NRC confirmatory analysis

- Discuss and reach agreement on anticipated FPL actions based on lessons learned from the Point Beach EPU

-- Summarize conservatisms in the analysis

-- Provide additional discussion on operational considerations for small break LOCAs

-- Confirmation that charging pumps trip on safety injection

-- Provide at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of margin between lineup for hot leg injection and the onset of boron precipitation

-- Other actions?

8 -FPL.

Nuclear Performance and Code Review Boric Acid Precipitation Timeline Injection Mode 1 RHR Pump, 2 HHSI Pumps

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.j Injection Mode 2 HHSI Pumps 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 10 minutes

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DelaY 1 T z - RWST Low Low Level Delay z l T. - Incipient Boric Acid Precipitation Without Hot Leg Recirculation T3 - HLSO Initiation Tl - RWST Low Level To - Event Initiation Tl - 15 minutes T z - 45 minutes To- Event Initation T3 - 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, 30 minutes T. - 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 40 minutes DelaYl - 2 minutes (EPU)

Delay z - 3 minutes (EPU) 9 I=PL.

Containment and Ventilation - EPITOME Analysis

• EPITOME code error involves LOCA mass and energy release calculation

• Turkey Point containment analysis is impacted

• Plant operability has been addressed

• EPU LOCA and MSLB analyses performed

- EPITOME code error correction

- Range for containment free volume

• Technical specification change proposed to lower limit on normal operating containment pressure from 3 psig to .

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- Include ITS improvement for administrative control of instrument air bleed 10 - I=PL.

Containment and Ventilation - EPITOME Analysis

• Other changes

- Modify the Emergency Containment Cooler (ECC) Start Logic to ensure 2 ECCs operate (new commitment)

- Reduce upper operating band on Tav9 from 3°F to 1.soF

- Other input changes

• Draft Results 11 - I=PL.

Containment and Ventilation - EPITOME LOCA Draft Results

- - - Containment Pressure. OEPS MINSI Contoinment Temperature. OEPS MINSI

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Containment and Ventilation - EPITOME MSLB Draft Results Containment Pressure . 1*0 sq ft Split Con tai nmen t Temperature. 30 % Power DER MSCV

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- FPL.

Containment and Ventilation - EPITOME

• Areas requiring revised analysis (applicable LAR sections in parentheses)

- Component Cooling Water Systems (2 .5.4.3)

- Primary Containment Functional Design (2.6.1)

- Mass and Energy Release (2 .6.3)

- Containment Heat Removal (2.6.5)

• Determined to be acceptable 14 -FPL.

Containment and Ventilation - EPITOME

• Other areas reviewed and determined no impact (applicable LAR sections in parentheses)

- Protective Coating Systems (2 .1.7)

- Balance of Plant Piping, Components and Supports (2 .2.2.2)

- Safety-Related Valves and Pumps (2.2.4)

- Environmental Qualification of Electrical Equipment (2 .3.1)

- Pressure Analysis for ECCS Performance Capability (2.6 .6)

- Containment Ventilation System (2 .7.7)

- ECCS and Loss-of-Coolant Accidents (2 .8.5.6.3)

- Radiological Consequences Analyses Using AST (2.9.2)

• No change to LAR section conclusions for impact of EPU 15 -FPL.

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Reactor Systems Branch Questions

• Received 31 non-LOCA RAls on 6/10/11

- Conducted clarification call on 6/20/11

- Preparing responses with a target issue of mid-July 2011

• Further discussion on the following:

- NUREG 0800 requirement regarding credited reactor trips for loss of load analysis

- Analysis of credible main steam line breaks

- eves malfunction in Modes 3, 4, and 5 (j

17 I=PL.

Reactor Systems Branch Questions

• Received additional RAls:

- 10on6/14/11

- 7on6/17/11

- Anticipate remaining questions by 6/23/11

- Clarification discussion today

- Preparing responses with a target of mid July 2011

• Further discussion on the following:

- Inadvertent opening of a PORV

- Additional information regarding LBLOCA nodalization 18 -FPL..

Reactor Systems Branch Questions

• RETRAN Deck

- Modified Turkey Point base deck to be compatible with RETRAN3D

- Westinghouse transmitted to NRC on 6/21/11

- Personnel available today to assist the Staff with running RETRAN with the modified base deck to ensure its compatibility with Staff software 19 - F=PL.

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Turkey Point - Closing

• FPL respond to remaining RAls and clarification requests

• Staff to complete remaining draft SE input

• Draft SE to ACRS Subcommittee in August

• Prepare for ACRS Subcommittee meeting in September and ACRS Full Committee meeting in October 21 -I=PL.