ML16177A048

2016/06/17 Indian Point 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

1 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

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 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

with the current operation of Unit 3.

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

is conservative.Plant equipment needed to shut down

would remain available during a pipeline

explosion.

13 14 Additional information/questionsContact Neil Sheehan, NRC Public Affairs Officer, at 610-337-5331 or via e-mail at

Neil.Sheehan@NRC.GOV