ML16047A133

February 9, 2016, Public Meeting Slides for License Amendment Request for Drain Down of Upper Containment Pool in Mode 3

ML16047A133
Person / Time
Site:	Perry
Issue date:	02/09/2016
From:	FirstEnergy Nuclear Operating Co
To:	Kimberly Green Plant Licensing Branch III
Green K, NRR/DORL/LPLIII-1
Shared Package
ML16053A345	List: ML16047A133
References
CAC MF7237
Download: ML16047A133 (25)

Text

FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant February 9, 2016

FENOC Representatives Tom Lentz - Manager Fleet Licensing Phil Lashley - Supervisor Fleet Licensing Al Rabenold - Supervisor Perry Plant Outage Management Jeff Haddick - Fleet Licensing Engineer Al Widmer - Fleet Engineering FENOC February 9, 2016 2

Agenda Meeting Objective Need for Amendment

Background

Supporting Analyses Proposed Technical Specification Changes Technical Evaluation Regulatory Evaluation Schedule Questions FENOC February 9, 2016 3

Meeting Objective Present information to NRC staff describing a proposed License Amendment Request (LAR) for the Perry Nuclear Power Plant (PNPP).

Answer questions from the NRC staff on the proposed LAR approach and obtain feedback from NRC staff on the proposed LAR content.

Identify the schedule associated with the LAR for its use in Perrys 16th refueling outage.

4 FENOC February 9, 2016

Need for Amendment The purpose of the proposed amendment is to allow certain outage-related activities to occur while in MODE 3.

- Installation of UCP reactor cavity to steam dryer storage pool gate (MODE 1, 2, and 3).

- Drain down of the reactor cavity pool (MODE 3).

Currently these activities are restricted to MODE 4 This Amendment will reduce critical path refueling time.

FENOC February 9, 2016 5

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Background===

FENOC February 9, 2016 6

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Background===

The Suppression Pool provides makeup water to the Reactor Pressure Vessel (RPV) in the event of a LOCA.

Design Basis for the Suppression Pool includes

- Maintaining 2 foot water coverage above horizontal vents

- Providing adequate NPSH for the ECCS pumps The Suppression Pool Makeup (SPMU) System provides makeup inventory to the Suppression Pool during a LOCA via gravity flow from the UCP.

The water level limits in the UCP and Suppression Pool are governed by PNPP Technical Specifications (TS).

FENOC February 9, 2016 7

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Background===

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FENOC February 9, 2016 11

Supporting Analyses Analyses have been performed to evaluate:

- UCP gate installation in MODES 1, 2, and 3.

- Drain down of the Reactor Cavity Pool in MODE 3 (with RPV pressure at 230 psig).

Impact of the UCP gate installation in MODES 1, 2, and 3.

- UCP water level needs to be maintained at the normal UCP water level (which is above the current TS minimum level).

- Suppression pool water level needs to be raised (within current TS operating band)

Impact of the Reactor Cavity Pool drain down in MODE 3 (with RPV pressure at 230 psig).

- Suppression Pool water level needs to be raised above the current TS HWL limit.

FENOC February 9, 2016 12

Proposed Technical Specification Changes TS 3.6.2.2 Suppression Pool Water Level FENOC February 9, 2016 13

Proposed Technical Specification Changes TS 3.6.2.4 Suppression Pool Makeup (SPMU) System FENOC February 9, 2016 14

Proposed Technical Specification Changes TS 3.6.2.4 Suppression Pool Makeup (SPMU) System FENOC February 9, 2016 15

Proposed Technical Specification Changes Add new Special Operations TS 3.10.9 Suppression Pool Makeup - MODE 3 Upper Containment Pool Drain Down FENOC February 9, 2016 16

Proposed Technical Specification Changes Add new Special Operations TS 3.10.9 Suppression Pool Makeup - MODE 3 Upper Containment Pool Drain Down (continued)

FENOC February 9, 2016 17

Proposed Technical Specification Changes FENOC February 9, 2016 18

Technical Evaluation Containment Response Using GOTHIC Computer Code Post-Accident Vent Coverage

• With UCP gate installed (MODES 1, 2, 3)

• With UCP reactor cavity fully drained (MODE 3)

• During UCP drain down evolution (TS figure developed)

ECCS NPSH Requirements Long-Term Heat Sink Personnel and LOCA Dose Evaluation Steam Line Break with Steam Bypass of Suppression Pool FENOC February 9, 2016 19

Technical Evaluation Hydrodynamic Loads

- Water Jet Loads

- LOCA Air Bubble Loads

- Pool Swell Drag and Impact Loads

- Fallback Loads

- Froth Impingement and Drag Loads

- Condensation Oscillation Loads

- Chugging Loads

- Drywell Depressurization Loads FENOC February 9, 2016 20

Technical Evaluation Miscellaneous Considerations

- Potential Drywell Flooding with Inadvertent UCP Dump

- UCP Dump Time versus SP Pump Time Criterion

- Evaluation of IFTS Blind Flange Removal During MODE 3 Drain Down Activity FENOC February 9, 2016 21

Regulatory Evaluation No Significant Hazards Consideration Applicable Regulatory Requirements/Criteria

- GDC 4 Environmental and Dynamic Effects Design Bases

- GDC 16 Containment Design

- GDC 38 Containment Heat Removal

- GDC 50 Containment Design Basis FENOC February 9, 2016 22

Regulatory Evaluation Precedent

- Grand Gulf Nuclear Station

- Clinton Power Station Environmental Consideration FENOC February 9, 2016 23

Schedule Schedule

- Approval requested in advance of Perry Refuel Outage 1R16 FENOC February 9, 2016 24

Questions Questions?

FENOC February 9, 2016 25