ML12199A300

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Lr - NextEra Seabrook ACRS Slides
ML12199A300
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 07/06/2012
From:
Office of Nuclear Reactor Regulation
To:
References
Download: ML12199A300 (35)
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Text

1 SeabrookNPEm Resource From:

Cunanan, Arthur Sent:

Friday, July 06, 2012 2:00 PM To:

Cliche, Richard

Subject:

RE: NextEra Seabrook ACRS slides Attachments:

Seabrook Sub ACRS Mtg 7-10-12.pptx

Rick, Attached are the Seabrook ACRS presentation slides.

Sincerely, Arthur Cunanan Project Manager Division of License Renewal U.S. Nuclear Regulatory Commission 301-415-3897 arthur.cunanan@nrc.gov From: Cliche, Richard [1]

Sent: Friday, July 06, 2012 1:55 PM To: Cunanan, Arthur; Howard, Kent

Subject:

NextEra Seabrook ACRS slides Rick Cliche License Renewal Project Manager Seabrook Station richard.cliche@fpl.com Desk: (603) 773-7003 Fax: (603) 773-7995 Cell: (603) 765-6358

Hearing Identifier:

Seabrook_License_Renewal_NonPublic Email Number:

3252 Mail Envelope Properties (Arthur.Cunanan@nrc.gov20120706135900)

Subject:

RE: NextEra Seabrook ACRS slides Sent Date:

7/6/2012 1:59:58 PM Received Date:

7/6/2012 1:59:00 PM From:

Cunanan, Arthur Created By:

Arthur.Cunanan@nrc.gov Recipients:

"Cliche, Richard" <Richard.Cliche@fpl.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 657 7/6/2012 1:59:00 PM Seabrook Sub ACRS Mtg 7-10-12.pptx 982052 Options Priority:

Standard Return Notification:

No Reply Requested:

No Sensitivity:

Normal Expiration Date:

Recipients Received:

Advisory Committee on Reactor Safeguards (ACRS)

License Renewal Subcommittee Safety Evaluation Report (SER)

Seabrook Station, Unit 1 (Seabrook)

Safety Evaluation Report (SER) with Open Items July 10, 2012 Arthur Cunanan, Project Manager Offi f N l

R t

R l ti 1

Office of Nuclear Reactor Regulation

Presentation Outline

  • SER Section 2, Scoping and Screening review
  • SER Section 4, Time-Limited Aging Analyses (TLAAs)

(TLAAs) 2

Overview

- Applicant: NextEra Energy Seabrook, LLC (NextEra)

Facility Operating License No NPF 86

- Facility Operating License No. NPF-86 requested renewal for a period of 20 years beyond the current license date of May 15, 2030 A

i t l 15 il th f P t

th NH

  • Approximately 15 miles south of Portsmouth, NH

Audits and Inspections

  • Scoping and Screening Methodology Audit

- September 20-23, 2010

- October 12-15, 2010

- October 18-22, 2010

  • Region I Inspection (Scoping and Screening &

g p

(

p g g

AMPs)

- March 7, 2010 - April 8, 2011 4

March 7, 2010 April 8, 2011

Overview (SER)

  • Safety Evaluation Report (SER) with Open Items i

d J 8 2012 issued June 8, 2012

  • SER contains 7 Open Items (OI):

SER contains 7 Open Items (OI):

- Bolting Integrity Program

- ASME Code Section XI, Subsection IWE Program Steam Generator Tube Integrity Program

- Steam Generator Tube Integrity Program

- Operating Experience

- Treated Borated Water

- Pressure-Temperature Limit

- Structures Monitoring Program 5

SER Section 2 Summary Structures and Components Subject to Aging Management Review

  • Section 2.1, Scoping and Screening Methodology M th d l i

i t t

ith th i

t f 10 CFR 54 4 d

g

- Methodology is consistent with the requirements of 10 CFR 54.4 and 10 CFR 54.21

  • Section 2.2, Plant-Level Scoping Results p g

- Systems and structures within the scope of license renewal are appropriately identified in accordance with 10 CFR 54.4 S

ti 2 3 2 4 2 5 S i

d S i

R lt

  • Sections 2.3, 2.4, 2.5 Scoping and Screening Results

- SSCs within the scope of license renewal are appropriately identified in accordance with 10 CFR 54.4(a), and those subject to an AMR in 6

( )

j accordance with 10 CFR 54.21(a)(1)

License Renewal Inspections p

Michael Modes Michael Modes Region I Inspection Team Leader Region I Inspection Team Leader

Regional Inspections Overview Four inspectors for 3 weeks 10 CFR 50.4 (a)(2) inspection, non-safety affecting safety portion y

g y p Selected Aging Management Programs f

th h

it i

for a more thorough onsite review 8

Regional Inspections AMP Inspection Results Buried Piping and Tanks Inspection p

Lubricating Oil Analysis g

y Fire Water System Fire Water System 9

Regional Inspections Additional Inspection Issue ASME Section XI, Subsection IWL Structures Monitoring Program 10

Regional Inspections Walk-downs Residual Heat Removal Turbine Building P i A

ili B ildi Primary Auxiliary Building East Main Steam & Feedwater Pipe Chase West Main Steam & Feedwater Pipe Chase C

t l B ildi Control Building Service Water Pumphouse Emergency Feedwater Pumphouse and Pre-Action Valve Building St G

t Bl d

B ildi Steam Generator Blowdown Building Emergency Diesel Generator Room B RCA Tunnel T

k F A

Tank Farm Area System Containment Exterior 11

Regional Inspections Observation and Findings Applicants review of the effects of alkali-silica reaction on structures was incomplete at the time of the inspection of the inspection Water intrusion was noted during RHR g

walk-down Deposits Deposits Brown Stains (Membrane Failure) 12

Regional Inspections Inspection Conclusions Scoping of non-safety SSCs and application of the AMPs to those SSCs were acceptable Except for the ASR issue, inspection results support a conclusion of reasonable assurance support a conclusion of reasonable assurance exists that aging effects will be managed and intended functions maintained Documentation supporting the application was auditable and retrievable auditable and retrievable 13

Section 3: Aging Management Review Management Review

g

  • Section 3.1 - Reactor Vessel & Internals
  • Section 3 2 - Engineered Safety Features Section 3.2 Engineered Safety Features
  • Section 3.3 - Auxiliary Systems
  • Section 3 4 Steam and Power Conversion System
  • Section 3.4 - Steam and Power Conversion System
  • Section 3.5 - Containments, Structures and Component Supports pp
  • Section 3.6 - Electrical and Instrumentation and Controls System 14

SER Section 3 3.0.3 - Aging Management Programs 42 Aging Management Programs (AMPs) presented by applicant and evaluated in the SER Consistent with GALL Consistent with exception Consistent with With exception &

Plant Specific t

G with exception with enhancement e cept o enhancement Specific Existing (29) 10 3

10 4

2

(

)

New (13) 6 3

1 3

15

SER Section 3 Open Items SER Section 3.0.3.1.7 - Bolting Integrity Program OI 3.0.3.1.7-1 Seal cap enclosures can contain water leakage that should be p

g managed for aging LRA does not contain AMR items that address bolting and external surfaces in seal cap enclosure environments, which may be submerged due to ongoing leakage within the enclosure 16

SER Section 3 Open Items SER Section 3.0.3.1.9 ASME Code Section XI, Subsection IWE Program OI 3.0.3.1.9-1 The applicant has not implemented procedures and inspection requirements to keep this area dewatered in the future 17

SER Section 3 Open Items SER Section 3.0.3.2 Steam Generator Tube Integrity Program OI 3.0.3.2.2-1 Cracking due to primary water stress corrosion cracking (PWSCC) on the primary coolant side of steam generator tube-to-tubesheet welds One-time inspection of the steam generator divider plate assembly 18

SER Section 3 Open Items SER Section 3.0.5 Operating Experience OI B.1.4-2 Details of future operating experience to ensure AMPs will p

g p

remain effective for managing the aging effects are not fully described 19

SER Section 3 Open Items SER Section 3.2.2.1 Treated Borated Water OI 3.2.2.1-1 Recently issued interim staff guidance (LR-ISG-2011-01) y g

(

)

recommends additional aging management activities for stainless steel components in treated borated water 20

SER Section 4: TLAA 4.1 Introduction 4.2 Reactor Vessel Neutron Embrittlement 4.3 Metal Fatigue Analysis g

y 4.4 Environmental Qualification of Electrical Equipment q p 4.5 Concrete Containment Tendon Prestress Analysis (not applicable to Seabrook) 4.6 Containment Liner Plate, Metal Containments, and Penetrations Fatigue Analysis 21 4.7 Other Plant-Specific TLAAs

SER Section 4 Open Item SER Section 4.2.4 Pressure-Temperature Limit OI 4.2.4-1 Concerns that the methodology used to develop the P-T limits are not consistent with the requirements in 10 CFR 50, Appendix G.

22

SER Section 3 Open Items SER Section 3.0.3.2.18 Structures Monitoring and Containment C

t I

i (IWL) I ti Concrete Inservice (IWL) Inspection Programs OI 3.0.3.2.18-1 The applicants enhancement to the Structures Monitoring Aging Management Program is not sufficient to manage the effects of ASR Th li t h t

h d th t i t IWL f

ASR The applicant has not enhanced the containment IWL program for ASR The applicant submitted an ASR monitoring program (May 16, 2012) 23

Conditions for Alkali Silica Reaction (ASR)

Reaction (ASR) 24

Effect of ASR on Concrete Aggregate containing silica reacts alkali hydroxides in the cement i

f t

in presence of water An alkali silica gel is formed Gel swells expands and cause internal stresses Patterned cracking in concrete due to expansion and swelling Patterned cracking in concrete due to expansion and swelling Degradation of mechanical properties of concrete 25

ASR at Seabrook Electrical Tunnel Tunnel 26

Seabrook Containment and Enclosure Building and Enclosure Building 30 Inch Thick Enclosure Wall Whit White Efflorescence at ASR Affected This Area Filled with Cracks 48 Inch Thick Containment Water up to 6 Feet Height Base Slab Containment Wall 27

Seabrook Operating Experience: Concrete Compressive strength and elastic modulus tests performed Experience: Concrete Degradation Due to ASR Compressive strength and elastic modulus tests performed Extent and rate of degradation of concrete over timenot completed p

Applicant does not plan to:

- Perform additional tests on concrete cores

- Extract cores from concrete containment and perform petrographic examination Applicant plans to perform large scale concrete beam tests Concrete expansion testsin process Absence of ASR can only be confirmed by petrographic examination of core samples p

Applicants approach for the aging management of ASR affected structures continues to evolve 28

SER Open Item OI 3 0 3 2 18 1: Containment Staffs Concerns Applicant observed cracking at two locations OI 3.0.3.2.18-1: Containment Applicant observed cracking at two locations

- Crack width no more than 8 mils Cracking pattern observed is indicative of ASR The applicant considers 8 mils maximum crack width insignificant

- Cracks due to ASR grow over time

- 15 mil crack width criteria is for passive cracks p

- GALL report and related industry standards require further evaluation of active cracks Absence of ASR can only be confirmed by petrographic examination Absence of ASR can only be confirmed by petrographic examination of core samples The applicant has not addressed the long term effects of ASR on degradation of mechanical properties of concrete The applicant has not enhanced the containment IWL program for ASR 29

SER Open Item OI 3.0.3.2.18-1: Other Structures Staffs Concerns

  • On March 30, 2012, the applicant committed to:

- Perform accelerated expansion testing

- Perform testing on full-scale replicas Perform testing on full scale replicas

- Determine crack limits and index based on test data

- Use test results to develop acceptance criteria

  • On May 16 2012 the applicant submitted ASR
  • On May 16, 2012, the applicant submitted ASR Monitoring Program AMP that is under review by the NRC staff

- Initial Observations:

  • Program acceptance criteria not based on full scale and expansion tests results
  • Acceptance criteria less stringent than industry standards
  • ASR detected by visual examination 30

Aging Management of ASR Affected Structures GALL Report recommends that the applicant augment the AMPs for the specific conditions and operating experience Affected Structures AMPs for the specific conditions and operating experience Applicant has proposed a plant specific AMP to manage AMP An acceptable AMP for ASR should be based on the An acceptable AMP for ASR should be based on the following:

- Baseline inspection of concrete structures to document current condition of structures

- Extent of aggregate reaction to date and remaining reactivity/expansion going forward reactivity/expansion going forward

- Extent and rate of degradation of mechanical properties

- Appropriate acceptance criteria based on test data and

- Appropriate acceptance criteria based on test data and additional analysis 31

SER Open Item OI 3 0 3 2 18 1: Summary The applicant has not yet demonstrated that it could OI 3.0.3.2.18-1: Summary pp y

adequately manage aging of the Seabrook concrete structures due to ASR for the period of extended operations operations 32

Conclusion Until the applicant can resolve all the open items, the staff can not make a conclusion that the requirement of 10 CFR 54.29(a) have been met for the license renewal of Seabrook Station the license renewal of Seabrook Station 33

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