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| number = ML16177A048
| number = ML16177A048
| issue date = 06/17/2016
| issue date = 06/17/2016
| title = 2016/06/17 Indian Point Lr Hearing - FW: IP Aam Slideshow
| title = Lr Hearing - FW: IP Aam Slideshow
| author name =  
| author name =  
| author affiliation = NRC
| author affiliation = NRC
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:1NPEmails, IPRenewalFrom:Dentel, GlennSent:Friday, June 17, 2016 9:04 AMTo:Martin, Jody
{{#Wiki_filter:NPEmails, IPRenewal From:                             Dentel, Glenn Sent:                             Friday, June 17, 2016 9:04 AM To:                               Martin, Jody


==Subject:==
==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
FW: IP AAM Slideshow Attachments:                       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:==
==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.  
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.
Brett/Neil, please review for appropriateness.
Thank you, Niklas Floyd Reactor Inspector Division of Reactor Safety USNRC Region I (610) 337-5282  
Thank you, Niklas Floyd Reactor Inspector Division of Reactor Safety USNRC Region I (610) 337-5282 1


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


==Subject:==
==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>
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:
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:
"Martin, Jody" <Jody.Martin@nrc.gov>
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.)
Tracking Status: None Post Office:
Degradation of Bolts (cont'd.)6 7Degradation of Bolts (cont'd.)
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:
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.)
Recipients Received:
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}}
Annual Assessment Meeting for Indian Point Nuclear Plant U.S. Nuclear Regulatory Commission June 8, 2016 1
 
NRC SPEAKERS David Lew, NRC Region I Deputy Administrator Ray Lorson, Director of the Division of Reactor Safety, Region I Glenn Dentel, Branch Chief in the Division of Reactor Projects, Region I Jack McHale, Chief of the Vessels & Internals Integrity Branch, NRCs Office of Nuclear Reactor Regulation Mike McCoppin, Chief of the Radiation Protection and Accident Consequences Branch, NRCs Office of New Reactors 2
 
Presentations on Plant Performance and Topics of Interest 3
 
Degradation of Baffle-former Bolts 4
 
Degradation of Bolts (contd.)
5
 
Degradation of Bolts (contd.)
6
 
Degradation of Bolts (contd.)
7
 
Summary of Bolt Degradation 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.
8
 
Installation of Pipeline 9
 
Thresholds for Damage Overpressure                              Consequence 1 psi          Glass shatters 2-6 psi          Serious structural damage to houses 6-9 psi          Severe damage to reinforced concrete structures 10 psi          Destruction of Buildings
* No safety-related structure necessary to safely shutdown IPEC exposed to >1 psi Thermal Heat Flux (KW/m2)                     Consequence 2            Pain within 60 sec 5            Tolerable to escaping personnel 12.6          Plastic melts 31.5          Building Damage
* Max heat flux at SOCA boundary found to be about 1/2 of that which melts plastic 10
 
Installation of Pipeline (Contd.)
11
 
Installation of Pipeline (Contd.)
12
 
Summary of Pipeline Installation Independent  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
 
Additional information/questions Contact  Neil Sheehan, NRC Public Affairs Officer, at 610-337-5331 or via e-mail at Neil.Sheehan@NRC.GOV 14}}

Latest revision as of 15:42, 4 December 2019

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

NPEmails, IPRenewal From: Dentel, Glenn Sent: Friday, June 17, 2016 9:04 AM To: Martin, Jody

Subject:

FW: IP AAM Slideshow Attachments: 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 1

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:

Annual Assessment Meeting for Indian Point Nuclear Plant U.S. Nuclear Regulatory Commission June 8, 2016 1

NRC SPEAKERS David Lew, NRC Region I Deputy Administrator Ray Lorson, Director of the Division of Reactor Safety, Region I Glenn Dentel, Branch Chief in the Division of Reactor Projects, Region I Jack McHale, Chief of the Vessels & Internals Integrity Branch, NRCs Office of Nuclear Reactor Regulation Mike McCoppin, Chief of the Radiation Protection and Accident Consequences Branch, NRCs Office of New Reactors 2

Presentations on Plant Performance and Topics of Interest 3

Degradation of Baffle-former Bolts 4

Degradation of Bolts (contd.)

5

Degradation of Bolts (contd.)

6

Degradation of Bolts (contd.)

7

Summary of Bolt Degradation 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.

8

Installation of Pipeline 9

Thresholds for Damage Overpressure Consequence 1 psi Glass shatters 2-6 psi Serious structural damage to houses 6-9 psi Severe damage to reinforced concrete structures 10 psi Destruction of Buildings

  • No safety-related structure necessary to safely shutdown IPEC exposed to >1 psi Thermal Heat Flux (KW/m2) Consequence 2 Pain within 60 sec 5 Tolerable to escaping personnel 12.6 Plastic melts 31.5 Building Damage
  • Max heat flux at SOCA boundary found to be about 1/2 of that which melts plastic 10

Installation of Pipeline (Contd.)

11

Installation of Pipeline (Contd.)

12

Summary of Pipeline Installation Independent 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

Additional information/questions Contact Neil Sheehan, NRC Public Affairs Officer, at 610-337-5331 or via e-mail at Neil.Sheehan@NRC.GOV 14

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