ML16177A048: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:1 NPEmails, IPRenewal From: Dentel, Glenn Sent: Friday, June 17, 2016 9:04 AM To: 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 Slideshow Attachments:
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)
Indian Point AAM 6-8-2016.pptx
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


Glenn Dentel Branch Chief responsible for oversight of Indian Point and Millstone 610-337-5233 (w)
==Subject:==
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 
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


Cc: McNamara, Nancy ; Screnci, Diane 
Hearing Identifier:   IndianPointUnits2and3NonPublic_EX Email Number:          7102 Mail Envelope Properties    (Glenn.Dentel@nrc.gov20160617090300)


==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.
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


Brett/Neil, please review for appropriateness.
Presentations on Plant Performance and Topics of Interest 3


Thank you,  Niklas Floyd Reactor Inspector
Degradation of Baffle-former Bolts 4


Division of Reactor Safety USNRC Region I (610) 337-5282
Degradation of Bolts (contd.)
5


Hearing Identifier:  IndianPointUnits2and3NonPublic_EX Email Number:  7102  Mail Envelope Properties  (Glenn.Dentel@nrc.gov20160617090300)
Degradation of Bolts (contd.)
6


==Subject:==
Degradation of Bolts (contd.)
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>
7
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 Plant U.S. Nuclear Regulatory Commission June 8, 2016 2 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, 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 Interest 3
Degradation of Baffle-former Bolts 4
5 Degradation of Bolts (cont'd.)
Degradation of Bolts (cont'd.)
6 7 Degradation 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  
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


with the current operation of Unit 3.
Installation of Pipeline 9
8 Summary of Bolt Degradation 9 Installation of Pipeline OverpressureConsequence1 psiGlass shatters2-6 psiSerious structural damage to houses 6-9 psiSevere damage to rein forced 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 plastic Thresholds for Damage 10 11 Installation of Pipeline (Cont'd.)
12 Installation of Pipeline (Cont'd.)
Summary of Pipeline InstallationIndependent and diverse analysis (NRC, Entergy, DOT) demonstrate no safety


impacts.Actual explosions confirmed NRC analysis
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


is conservative.Plant equipment needed to shut down
Installation of Pipeline (Contd.)
11


would remain available during a pipeline
Installation of Pipeline (Contd.)
12


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


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

Revision as of 18:27, 30 October 2019

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

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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