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NPEmails, IPRenewal

From: Dentel, GlennSent: Friday, June 17, 2016 9:04 AMTo: Martin, JodySubject: 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:

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Annual Assessment Meeting for Indian Point Nuclear Plant

U.S. Nuclear Regulatory CommissionJune 8, 2016

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NRC SPEAKERSDavid 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

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Degradation of Baffle-former Bolts

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Degradation of Bolts (cont’d.)

Degradation of Bolts (cont’d.)

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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 with the current operation of Unit 3.

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Summary of Bolt Degradation

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Installation of Pipeline

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

Thermal Heat Flux (KW/m2) Consequence

2 Pain within 60 sec

5 Tolerable to escaping personnel

12.6 Plastic melts

31.5 Building Damage

• No safety-related structure necessary to safely shutdown IPEC exposed to >1 psi

• Max heat flux at SOCA boundary found to be about ½ of that which melts plastic

Thresholds for Damage

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Installation of Pipeline (Cont’d.)

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Installation of Pipeline (Cont’d.)

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.

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Additional information/questions

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