ML11077A033

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Lr Hearing - Draft Slides
ML11077A033
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 02/24/2009
From: Kimberly Green
License Renewal Projects Branch 2
To: Stroud M
- No Known Affiliation
References
Download: ML11077A033 (48)
v • d • e


Text

1 Stuyvenberg, Andrew From:

Green, Kimberly Sent:

Tuesday, February 24, 2009 8:09 AM To:

STROUD, MICHAEL D

Subject:

Draft Slides Attachments:

ACRS-Indian Point-Presentation 02-24-09.ppt

Mike, Here are the draft slides. As you can see, I'm still working on the last few (open items).

I've been requested to develop back up slides for items that have been raised in the most recent meetings.

They will not be a part of the slide package that is available at the meeting since I may not have to use them.

I'm having another dry run tomorrow. I will send the final slides by the end of the week. Should anything change between then and the meeting on the 4th, I will let you know.

Kim

Advisory Committee on Reactor Safeguards License Renewal Subcommittee Indian Point Nuclear Generating Unit Indian Point Nuclear Generating Unit Nos. 2 and 3 Safety Evaluation Report with Open Items March 4, 2009 Kimberly Green, Project Manager Office of Nuclear Reactor Regulation

Introduction

  • Overview
  • Section 2: Scoping and Screening Review
  • Section 4: Time-Limited Aging Analyses (TLAAs)
  • Open Items

Overview

  • 3216 MWth, 1080 MWe
  • Operating license DPR-26 (IP2) expires Operating license DPR 26 (IP2) expires September 28, 2013
  • Operating license DPR-64 (IP3) expires December 12 2015 December 12, 2015
  • Located approximately 25 miles north of NYC limits

Overview

  • Safety Evaluation Report with Open Items was i

d J 15 2009 issued January 15, 2009

  • 20 Open items
  • 272 Audit Questions
  • 38 Commitments

Overview Scoping and Screening Methodology Audit

- October 8, 2007 - October 12, 2007 Aging Management Programs (AMP) Audit Aging Management Programs (AMP) Audit

- August 27, 2007 - August 31, 2007 Aging Management Review (AMR) & Time-Limited Aging Analysis (TLAA) Audit O t b 22 2007 O t b 26 2007

- October 22, 2007 - October 26, 2007

- November 27, 2007 - November 29, 2007

- February 19, 2008 - February 21, 2008 Regional License Renewal Inspections eg o a ce se e e a spect o s

- January 28, 2008 - February 1, 2008

- February 11, 2008 - February 14, 2008

- March 31, 2008 - April 2, 2008 J

2 2008 J

6 2008 d J 18 2008

- June 2, 2008 - June 6, 2008, and June 18, 2008

Open Items

  • SER issued with 20 open items

- 14 with requests for additional information

- 6 are still under review by staff

  • Applicant submitted additional information dated January 27, 2009
  • Staff has closed out 13 Open Items

Section 2: Structures and Components Subject to Aging Management Review Section 2.1 - Scoping and Screening Methodology Subject to Aging Management Review

  • Based on audit and review staff concluded that the applicants methodology is consistent with the requirements of 10 CFR 54.4 and 54.21(a)(1) requirements of 10 CFR 54.4 and 54.21(a)(1)

Section 2.2 - Plant-Level Scoping Results

  • IP2 chlorination and IP3 H2 systems initially omitted from scope

Section 2: Structures and Components Subject to Aging Management Review Section 2.3 - Scoping and Screening Results:

Mechanical Systems Subject to Aging Management Review Mechanical Systems

  • Mechanical Systems: 59 (IP2 ) and 87 (IP3)
  • Two Tier Review of Balance of Plant systems:
  • Two Tier Review of Balance of Plant systems:

- Tier 1 Review: Review LRA and UFSAR

- Tier 2 Review: Detailed review of LRA, UFSAR, and license renewal drawings

  • 100% of mechanical systems identified by applicant as within the scope of license renewal applicant as within the scope of license renewal were reviewed

Section 2: Structures and Components Subject to Aging Management Review Section 2.3 - Scoping and Screening Results:

M h

i l S t

Subject to Aging Management Review Mechanical Systems

  • Staff identified omission of nonsafety-related components from scope for IP2 containment components from scope for IP2 containment spray
  • Applicant re evaluated and identified 3 other
  • Applicant re-evaluated and identified 3 other systems (IP2 CCW, IP3 CCW, and IP3 BVS)
  • Amended LRA and added components to scope
  • Amended LRA and added components to scope

Section 2: Structures and Components Subject to Aging Management Review Subject to Aging Management Review Section 2.3 - Scoping and Screening Results M

h i

l S t

Mechanical Systems

  • Three Open Items

- OI 2.3A.3.11 yard hose houses and chamber housings

- OI 2 3 4 2 feedwater isolation valves OI 2.3.4.2 1 feedwater isolation valves

- OI 2.3A.4.5 auxiliary feedwater pump room fire event systems

  • These OIs have been closed

Section 2: Structures and Components Subject to Aging Management Review Subject to Aging Management Review Section 2.4 - Scoping and Screening Results:

St t

Structures

  • Staff concluded that there were no omissions of t

t t

t l

t f structures or structural components from scope of license renewal in accordance with 10 CFR 54 4(a) and no omissions from AMR in 54.4(a), and no omissions from AMR in accordance with 10 CFR 54.21(a)(1).

Section 2: Structures and Components Subject to Aging Management Review Subject to Aging Management Review Section 2.5 - Scoping and Screening Results:

Electrical and Instrumentation and Control Electrical and Instrumentation and Control Systems

  • OI 2.5 Station blackout scoping
  • Issue is under staff evaluation
  • With exception of SBO OI scoping, staff concluded no omission of electrical and concluded no omission of electrical and instrumentation and control system components from the scope of license renewal in accordance with 10 CFR 54 4(a) and no omissions from with 10 CFR 54.4(a), and no omissions from AMR in accordance with 10 CFR 54.21(a)(1)

Section 2: Structures and Components Subject to Aging Management Review Subject to Aging Management Review Section 2.6 - Conclusion for Scoping and Screening Screening

  • The applicants scoping and screening methodology is consistent with the requirements methodology is consistent with the requirements of 10 CFR 54.4 and 10 CFR 54.21(a)(1)
  • With exception of open items, the applicant adequately identified those SSCs within the scope of license renewal in accordance with 10 CFR 54 4(a) and those SCs subject to an AMR CFR 54.4(a), and those SCs subject to an AMR in accordance with 10 CFR 54.21(a)(1).

License Renewal Inspections License Renewal Inspections Glenn Meyer Glenn Meyer Region I Inspection Team Leader Region I Inspection Team Leader

Inspection Objectives p

j

  • Scoping of Non-safety SSCs
  • Scoping of Non-safety SSCs

Programs (AMPs)

  • Review of 2 Systems
  • Followup: IP2 SBO diesel, cable vault, and containment liner

Scoping Scoping

  • Scoping of non-safety SSCs - generally
  • Scoping of non-safety SSCs - generally accurate and acceptable
  • Structural and spatial interactions
  • Structural and spatial interactions reviewed AMP i

f d 2 t

i

  • AMP reviews found 2 component scoping errors

Existing AMPs g

LRA Amendment

  • Structural Monitoring
  • Oil Analysis Oil Analysis
  • Diesel Fuel Monitoring W t Ch i t
  • Water Chemistry
  • Metal-Enclosed Bus Inspection

Existing AMPs g

Other Issues

  • Exposed rebar on containment
  • Operating Experience for Metal-Enclosed p

g p

Bus

  • Instrument air heat exchangers Instrument air heat exchangers
  • AMR for transite material CR i

l t d d d ti

  • CRs on isolated degradation

New AMPs

  • Selective Leaching
  • Selective Leaching
  • Non-EQ Bolted Cable Connections

Follow Up Inspections p

p

  • IP2 SBO diesel - scoping and system
  • IP2 SBO diesel - scoping and system review
  • Electrical cable vault
  • Electrical cable vault
  • Unit 2 containment liner

Inspection Conclusions p

  • Non-safety scoping and aging
  • Inspection results support a conclusion of bl th t i

ff t

reasonable assurance that aging effects will be managed and intended functions ill b i t i d

will be maintained

Section 3: Aging Management Review R

lt Results

  • Section 3.1 - Reactor Vessel & Internals
  • Section 3.2 - Engineered Safety Features
  • Section 3.3 - Auxiliary Systems
  • Section 3.4 - Steam and Power Conversion System
  • Section 3.5 - Containments, Structures and Component Supports
  • Section 3 6 Electrical and Instrumentation and Controls
  • Section 3.6 - Electrical and Instrumentation and Controls System

Section 3: Aging Management Review R

lt Section 3.0.3 - Aging Management Programs (AMP )

Results (AMPs)

- 10 New Programs

- 31 Existing Programs 15 consistent with GALL Report

  • 15 consistent with GALL Report
  • 18 consistent with GALL Report with enhancements and/or exceptions and/or exceptions
  • 8 plant-specific

Section 3: Aging Management Review R

lt Section 3.0.3 - AMPs Results

  • 8 Open Items
  • The following 5 OIs have been closed

- OI 3 0 3 2 7 fire penetration seals OI 3.0.3.2.7 1 fire penetration seals

- OI 3.0.3.3.3 acceptance criteria for visual examinations

- OI 3.0.3.3.4 inspection methods, etc. for lubrite sliding supports supports

- OI 3.0.3.3.4 corrective actions for ISI

- OI 3.0.3.3.7 Periodic Surveillance and Preventive Maintenance Program g

Section 3: Aging Management Review R

lt Section 3.0.3 - AMPs Results

  • The following 3 OIs are still under review

- OI 3.0.3.2.15 IP2 reactor refueling cavity OI 3.0.3.2.15 1 IP2 reactor refueling cavity leakage

- OI 3.0.3.2.15 IP2 spent fuel pool leak p

p

- OI 3.0.3.3.2 Exterior containment concrete degradation g

Section 3: Aging Management Review R

lt Section 3.1 - Aging Management of Results Reactor Vessel, Internals, and RCS

  • OI 3.1.2.2.7 Inspection of CASS Th 2 OI h b

l d

These 2 OIs have been closed

Section 3: Aging Management Review R

lt Section 3.3 - Aging Management of Results Auxiliary Systems

  • OI 3 3 Clarification of OI 3.3 1 Clarification of material/environment/aging effect for titanium components titanium components This OI has been closed

Section 3: Aging Management Review R

lt Section 3.4 - Aging Management of Results Steam and Power Conversion Systems Systems

Section 3: Aging Management Review R

lt Section 3.5 - Aging Management of Results Containments, Structures and Component Supports Component Supports

  • These 2 OIs are still under staff review OI 3 5 1 Water cement ratio for IP concrete

- OI 3.5 Water-cement ratio for IP concrete

- OI 3.5 Reduction of strength and modulus of concrete due to elevated temperatures of concrete due to elevated temperatures

Section 3: Aging Management Review R

lt Section 3.5 - Aging Management of Results Containments, Structures and Component Supports Component Supports

  • OI 3.5 Aging management of concrete surrounding B1 supports surrounding B1 supports This OI has been closed

Section 3: Aging Management Review R

lt Section 3.6 - Aging Management of El i

l d I&C S Results Electrical and I&C Systems

  • LRA identified no aging effects for IP2 138-kV hi h lt bl high-voltage cable
  • Staff issued RAI Applicant amended LRA to add cable to
  • Applicant amended LRA to add cable to Periodic Surveillance and Preventive Maintenance Program g

Section 3: Aging Management Review C

l i

Results Conclusion With the exception of the Open Items, the With the exception of the Open Items, the applicant has demonstrated that aging effects will be adequately managed during q

y g

g the period of extended operation in accordance with 10 CFR 54.21(a)(3)

Section 4: Time-Limited Aging Analyses

  • 4.1 Identification of Time Limited Aging Analyses (TLAAs) g g

y (TLAAs)

  • 4.2 Reactor Vessel Neutron Embrittlement
  • 4.3 Metal Fatigue 4.3 Metal Fatigue
  • 4.4 Environmental Qualification of Electrical Equipment
  • 4.5 Concrete Containment Tendon Prestress
  • 4.7 Other Plant-Specific TLAAs

Section 4.2: Reactor Vessel Neutron Embrittlement - Upper Shelf Energy Embrittlement Upper Shelf Energy Limiting Beltline MaterialLower Shell Plate (B2002-3)

Unit 2

% CU 48 EFPY Fluence (E>1 MeV) at Initial Charpy V notch USE Value Irradiated Charpy V Acceptance Criterion per Unit 2

(

)

1/4T 1019 (n/cm2)

(ft-lb) notch USE Value at 48 EFPY (ft-lb) 10 CFR 50, App. G (ft-lb) 0.25 1.136 74 48.3

>50

Section 4.2: Reactor Vessel Neutron Embrittlement - Upper Shelf Energy Embrittlement Upper Shelf Energy Limiting Beltline MaterialLower Shell Plate (B2803-3)

Unit 3

% CU 48 EFPY Fluence (E>1 MeV) at Initial Charpy V notch USE Value Irradiated Charpy V Acceptance Criterion per Unit 3

(

)

1/4T 1019 (n/cm2)

(ft-lb) notch USE Value at 48 EFPY (ft-lb) 10 CFR 50, App. G (ft-lb) 0.24 0.9298 68 49.8

>50

Section 4.2: Reference Temperature for Pressurized Thermal Shock (PTS) Values Pressurized Thermal Shock (PTS) Values Limiting Beltline MaterialLower Shell Plate (B2803-3)

Unit 3

%CU

%Ni 48 EFPY Fluence (E>1 MeV)

(@clad/steel interface)

Initial Charpy RTNDT 0F RTPTS 0F Acceptance Criterion per 10 CFR 50.61

(@clad/steel interface) 1019 (n/cm2)

F 0F 0.24 0.52 1.56 74 279.5

<270oF 0.52 Commitment 32: As required by 10 CFR 50.61(b)(4), IP3 will submit a plant-specific safety analysis for plate B2803-3 to the NRC three years prior to reaching the RTPTS safety analysis for plate B2803 3 to the NRC three years prior to reaching the RTPTS screening criterion. Alternatively, the site may choose to implement the revised PTS rule when approved.

Section 4.3: Metal Fatigue Analyses

  • 60-year fatigue analyses were performed g

y for all NUREG/CR-6260 locations, except 2 locations (IP2) and 3 locations (IP3)

)

Section 4: Time-Limited Aging Analyses Section 4.3 - Class 1 Fatigue g

g y

g

  • OI 4.3 Number of IP3 plant heatups and cooldowns and cooldowns This OI has been closed

Open Items

  • OI 3.0.3.2.15 IP2 reactor refueling cavity leakage
  • OI 3.0.3.2.15 IP2 spent fuel pool leak
  • OI 3.0.3.3.2 Exterior containment concrete d

d ti degradation

  • OI 3.5 Water-cement ratio for IP concrete
  • OI 3.5 Reduction of strength and modulus of concrete due to elevated temperatures

Open Items p

- By letter dated November 16 2007 the applicant revised LRA Figures By letter dated November 16, 2007, the applicant revised LRA Figures 2.5-2 and 2.5-3, the Offsite Power Scoping Diagram(s) for IP2 and IP3, to address staff concerns regarding the IP2 and IP3 primary and secondary offsite power paths.

- By letter dated March 24, 2008, the applicant revised its response to RAI 2.5-1.

- By letter dated August 14, 2008, the applicant clarified its response to RAI 2 5 1 RAI 2.5-1.

- The staff is completing its review of the applicants information on the SBO scoping boundary and will document its conclusion in the final SER.

SER.

Open Items p

  • OI 3.0.3.2.15 IP2 reactor refueling cavity leakage

- The reactor cavity at IP2 has a history of leakage at the upper The reactor cavity at IP2 has a history of leakage at the upper elevations of the stainless steel cavity liner when flooded during refueling outages.

- Attempts have been made over the last several outages to mitigate this condition, with limited success.

- An action plan is being developed for a permanent fix to this issue.

- Entergy has committed to perform a one-time inspection prior to f

f f

entering the period of extended operation to confirm the absence of degradation (Commitment 36).

- Entergy made no commitment for augmented inspection during the extended period of operation extended period of operation.

Open Items p

  • OI 3.0.3.2.15 IP2 spent fuel pool leak

Open Items p

  • OI 3.0.3.3.2 Exterior containment concrete degradation degradation

Open Items p

Open Items p

  • OI 3.5 Water-cement ratio for IP concrete

Open Items p

  • OI 3.5 Reduction of strength and modulus of concrete due to elevated temperatures concrete due to elevated temperatures

Questions?

Questions?

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