ML16177A048

Lr Hearing - FW: IP Aam Slideshow

ML16177A048
Person / Time
Site:	Indian Point
Issue date:	06/17/2016
From:	NRC
To:	Division of License Renewal
References
Download: ML16177A048 (16)

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.

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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.)

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Installation of Pipeline (Contd.)

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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