ML16177A048: Difference between revisions

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{{#Wiki_filter:1NPEmails, IPRenewalFrom:Dentel, GlennSent:Friday, June 17, 2016 9:04 AMTo:Martin, Jody
==Subject:==
FW: IP AAM SlideshowAttachments:Indian Point AAM 6-8-2016.pptx Glenn Dentel Branch Chief responsible for oversight of Indian Point and Millstone 610-337-5233 (w)  From: Floyd, Niklas  Sent: Tuesday, June 07, 2016 3:34 PM To: Lew, David ; Lorson, Raymond ; Dentel, Glenn ; Gray, Mel ; McCoppin, Michael ; McHale, John ; Klukan, Brett ; Sheehan, Neil ; Tifft, Doug ; Haagensen, Brian ; Rich, Sarah Cc: McNamara, Nancy ; Screnci, Diane 
==Subject:==
IP AAM Slideshow  Attached is the Indian Point Annual Assessment Meeting presentation for tomorrow night. I will print out several copies for those who wish to have a hardcopy at the meeting.
Brett/Neil, please review for appropriateness.
Thank you,  Niklas Floyd Reactor Inspector Division of Reactor Safety USNRC Region I (610) 337-5282
Hearing Identifier:  IndianPointUnits2and3NonPublic_EX  Email Number:  7102  Mail Envelope Properties  (Glenn.Dentel@nrc.gov20160617090300) 
==Subject:==
FW: IP AAM Slideshow  Sent Date:  6/17/2016 9:03:52 AM  Received Date:  6/17/2016 9:03:00 AM  From:    Dentel, Glenn  Created By:  Glenn.Dentel@nrc.gov  Recipients:    "Martin, Jody" <Jody.Martin@nrc.gov>
Tracking Status: None  Post Office:      Files    Size      Date & Time  MESSAGE    755      6/17/2016 9:03:00 AM Indian Point AAM 6-8-2016.pptx    4228957  Options  Priority:    Standard  Return Notification:    No  Reply Requested:    No  Sensitivity:    Normal  Expiration Date:      Recipients Received:
1Annual Assessment Meeting for Indian Point Nuclear PlantU.S. Nuclear Regulatory CommissionJune 8, 2016 2NRC SPEAKERSDavid Lew, NRC Region I Deputy AdministratorRay Lorson, Director of the Division of Reactor Safety, Region IGlenn Dentel, Branch Chief in the Division of Reactor Projects, Region IJack McHale, Chief of the Vessels & Internals Integrity Branch, NRC's Office of Nuclear Reactor Regulation Mike McCoppin, Chief of the Radiation Protection and Accident Consequences Branch, NRC's Office of New Reactors Presentations on Plant Performance and Topics of Interest3 Degradation of Baffle-former Bolts4 5Degradation of Bolts (cont'd.)
Degradation of Bolts (cont'd.)6 7Degradation of Bolts (cont'd.)
The degraded bolts were identified through required inspections.Unit 2 is safe to restart based on bolt replacements and supporting analyses.There are no immediate safety concerns with the current operation of Unit 3.8Summary of Bolt Degradation 9Installation of Pipeline OverpressureConsequence1 psiGlass shatters2-6 psiSerious structural damage to houses 6-9 psiSevere damage to reinforced concrete structures10 psiDestruction of BuildingsThermal Heat Flux (KW/m2)Consequence2Pain within 60 sec5Tolerable to escaping personnel12.6Plastic melts 31.5Building Damage*Nosafety-related structure necessary to safely shutdown IPEC exposed to >1 psi*Max heat flux at SOCA boundary found to be about 1/2 of that which melts plasticThresholds for Damage10 11Installation of Pipeline (Cont'd.)
12Installation of Pipeline (Cont'd.)
Summary of Pipeline InstallationIndependent and diverse analysis (NRC, Entergy, DOT) demonstrate no safety impacts.Actual explosions confirmed NRC analysis is conservative.Plant equipment needed to shut down would remain available during a pipeline explosion.13 14Additional information/questionsContact Neil Sheehan, NRC Public Affairs Officer, at 610-337-5331 or via e-mail at Neil.Sheehan@NRC.GOV
}}
}}

Revision as of 17:07, 14 May 2018

2016/06/17 Indian Point Lr Hearing - FW: IP Aam Slideshow
ML16177A048
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 06/17/2016
From:
NRC
To:
Division of License Renewal
References
Download: ML16177A048 (16)
v • d • e


Text

1NPEmails, IPRenewalFrom:Dentel, GlennSent:Friday, June 17, 2016 9:04 AMTo:Martin, Jody

Subject:

FW: IP AAM SlideshowAttachments:Indian Point AAM 6-8-2016.pptx Glenn Dentel Branch Chief responsible for oversight of Indian Point and Millstone 610-337-5233 (w) From: Floyd, Niklas Sent: Tuesday, June 07, 2016 3:34 PM To: Lew, David ; Lorson, Raymond ; Dentel, Glenn ; Gray, Mel ; McCoppin, Michael ; McHale, John ; Klukan, Brett ; Sheehan, Neil ; Tifft, Doug ; Haagensen, Brian ; Rich, Sarah Cc: McNamara, Nancy ; Screnci, Diane

Subject:

IP AAM Slideshow Attached is the Indian Point Annual Assessment Meeting presentation for tomorrow night. I will print out several copies for those who wish to have a hardcopy at the meeting.

Brett/Neil, please review for appropriateness.

Thank you, Niklas Floyd Reactor Inspector Division of Reactor Safety USNRC Region I (610) 337-5282

Hearing Identifier: IndianPointUnits2and3NonPublic_EX Email Number: 7102 Mail Envelope Properties (Glenn.Dentel@nrc.gov20160617090300)

Subject:

FW: IP AAM Slideshow Sent Date: 6/17/2016 9:03:52 AM Received Date: 6/17/2016 9:03:00 AM From: Dentel, Glenn Created By: Glenn.Dentel@nrc.gov Recipients: "Martin, Jody" <Jody.Martin@nrc.gov>

Tracking Status: None Post Office: Files Size Date & Time MESSAGE 755 6/17/2016 9:03:00 AM Indian Point AAM 6-8-2016.pptx 4228957 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:

1Annual Assessment Meeting for Indian Point Nuclear PlantU.S. Nuclear Regulatory CommissionJune 8, 2016 2NRC SPEAKERSDavid Lew, NRC Region I Deputy AdministratorRay Lorson, Director of the Division of Reactor Safety, Region IGlenn Dentel, Branch Chief in the Division of Reactor Projects, Region IJack McHale, Chief of the Vessels & Internals Integrity Branch, NRC's Office of Nuclear Reactor Regulation Mike McCoppin, Chief of the Radiation Protection and Accident Consequences Branch, NRC's Office of New Reactors Presentations on Plant Performance and Topics of Interest3 Degradation of Baffle-former Bolts4 5Degradation of Bolts (cont'd.)

Degradation of Bolts (cont'd.)6 7Degradation of Bolts (cont'd.)

The degraded bolts were identified through required inspections.Unit 2 is safe to restart based on bolt replacements and supporting analyses.There are no immediate safety concerns with the current operation of Unit 3.8Summary of Bolt Degradation 9Installation of Pipeline OverpressureConsequence1 psiGlass shatters2-6 psiSerious structural damage to houses 6-9 psiSevere damage to reinforced concrete structures10 psiDestruction of BuildingsThermal Heat Flux (KW/m2)Consequence2Pain within 60 sec5Tolerable to escaping personnel12.6Plastic melts 31.5Building Damage*Nosafety-related structure necessary to safely shutdown IPEC exposed to >1 psi*Max heat flux at SOCA boundary found to be about 1/2 of that which melts plasticThresholds for Damage10 11Installation of Pipeline (Cont'd.)

12Installation of Pipeline (Cont'd.)

Summary of Pipeline InstallationIndependent and diverse analysis (NRC, Entergy, DOT) demonstrate no safety impacts.Actual explosions confirmed NRC analysis is conservative.Plant equipment needed to shut down would remain available during a pipeline explosion.13 14Additional information/questionsContact Neil Sheehan, NRC Public Affairs Officer, at 610-337-5331 or via e-mail at Neil.Sheehan@NRC.GOV

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