Oral presentation

[2O01-05] Plant PRA

Thu. Sep 6, 2018 9:30 AM - 10:55 AM Room O (D25 -D Building)

Chair:Koichi Nakamura(CRIEPI)

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9:30 AM - 9:45 AM

[2O01] Consideration of KK-7 Internal Events Shutdown Level 1PRA Upgrade

(1) Issues Based on Internal Events At-Power Level 1PRA Upgrade

*Yoshikazu Ootaki¹, Issei Hidaka¹, Toshiteru Saitou¹, Satoshi Kawaguchi², Toshinobu Kita² (1. TEPCO SYSTEMS CORPORATION, 2. Tokyo Electric Power Company Holdings,Inc)

9:45 AM - 10:00 AM

[2O02] Consideration of KK-7 Internal Events At-Power Level1.5 PRA Upgrade

(1) Issues Based on Internal Events At-Power Level1 PRA Upgrade

*Takashi Masutani¹, Masatoshi Moteki¹, Natsuki Shiraishi¹, Chikahiro Satou¹, Masayuki Hiraide², Toshinobu Kita² (1. TEPCO SYSTEMS CORPORATION, 2. Tokyo Electric Power Company Holdings, Inc.)

10:00 AM - 10:15 AM

[2O03] The Progress of PRA for Tokai No.2 Power Station

(2)Extraction of Initiating event candidate "Implementation of failure mode effect analysis"

*Hiroto Matsumoto¹, Masaru Yamanaka², Takayuki Negishi¹, Atsuo Ikeda¹ (1. Nuclear Engineering and Services Company, 2. The Japan Atomic Power Company)

10:15 AM - 10:30 AM

[2O04] The Progress of PRA for SHIKA NPS unit2

(5)Evaluation Results of Level 1.5PRA During Power Operation Considering SA Equipment

*Takuma Takahashi², Mutsuhiro Nakada¹, Toshihiro Aida¹, Daisuke Suimon¹, Keisuke Takashima^1,2, Shinichi Hamatani^1,2, Takayuki Negishi², Atsuo Ikeda² (1. Hokuriku Electric Power Company, 2. Nuclear Engineering and Services Company)

10:30 AM - 10:45 AM

[2O05] The Progress of PRA for SHIKA NPS unit2

(6)Development of Core Damage Monitoring Tool During Power Operation(Level1 PRA)

*Keisuke Takashima^1,2, Mutsuhiro Nakada², Toshihiro Aida², Daisuke Suimon², Takayuki Negishi¹, Atsuo Ikeda¹, Junya Masuko¹ (1. Nuclear Engineering and Services Company, 2. Hokuriku Electric Power Company)

Time reserved for Chair （10:45 AM - 10:55 AM）

Oral presentation

[2O06-09] PRA Improvement

Thu. Sep 6, 2018 10:55 AM - 12:00 PM Room O (D25 -D Building)

Chair:Hitoshi Muta(Tokyo City Univ.)

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10:55 AM - 11:10 AM

[2O06] Assessment of LOCA Considering the Partial Fracture of Pipes on Level 1 PRA

*Kohei Yoshida¹, Daichi Shiota¹, Yuki Ishiwatari¹, Kyohei Echizen² (1. Hitachi-GE Nuclear Energy, Ltd., 2. Hitachi Industry & Control Solutions, Ltd.)

11:10 AM - 11:25 AM

[2O07] Development of the evaluation method for the advanced level 2 probabilistic risk assessment

(9) Applicability study of the Source Term PRD to the ADAPT method

*Koichi Nakamura¹, Yoko Yamane², Keigo Murata² (1. Central Research Institute of Electric Power Industry, 2. Advancesoft Corporation)

11:25 AM - 11:40 AM

[2O08] Development of the evaluation method for the advanced level 2 probabilistic risk assessment

(10) Consideration of Source term PRD method for a variety of scenarios expected in the SBO scenario

*Yoko Yamane¹, Koichi Nakamura², Keigo Murata¹ (1. Advancesoft Corporation, 2. Central Research Institute of Electric Power Industry)

11:40 AM - 11:55 AM

[2O09] Development of the evaluation method for the advanced level 2 probabilistic risk assessment.

(11)Evaluation of cesium re-evaporation amount depending on dispersion state of molten debris in containment vessel.

*KEIGO MURATA¹, Koichi Nakamura², Yoko Yamane¹ (1. AdvanceSoft Corporation, 2. Central Research Institute of Electric Power Industry)

Time reserved for Chair （11:55 AM - 12:00 PM）

Oral presentation

[2O10-11] PRA Application

Thu. Sep 6, 2018 2:45 PM - 3:20 PM Room O (D25 -D Building)

Chair:Hiroshi Ujita(AdvanceSoft)

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2:45 PM - 3:00 PM

[2O10] Application of human reliability analysis methods to fuel cycle facilities

*Makoto Takizawa¹, Kenji Mori¹, Kazuki Yamate¹, Kazuo Kubota¹ (1. Secretariat of Nuclear Regulation Authority)

3:00 PM - 3:15 PM

[2O11] Accident Model STAMP for Risk Management of Nuclear Power Station Against External Natural Events

Part 1: STAMP Model for External Events

*Yasuki Ohtori¹, Hitoshi Muta¹, Akira Omoto^2,1 (1. Tokyo City University, 2. Tokyo Institute of Technology)

Time reserved for Chair （3:15 PM - 3:20 PM）

Oral presentation

[1P01-07] PRA Methodology

Wed. Sep 5, 2018 10:00 AM - 11:55 AM Room P (E21 -E Building)

Chair:Katsumi Ebisawa(CRIEPI)

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10:00 AM - 10:15 AM

[1P01] Internal Flooding PSA of ABWR

*Kyohei Echizen¹, Yuki Ishiwatari², Daichi Shiota², Takashi Sumikawa² (1. Hitachi Industry & Control Solutions, Ltd., 2. Hitachi-GE Nuclear Energy, Ltd.)

10:15 AM - 10:30 AM

[1P02] Establishment of Internal Fire PRA Guide for Japanese NPPs

*Tsuyoshi Uchida¹, Koji Shirai¹, Hiroyuki Takeuchi², Shingo Oda³, Kohei Sugita⁴ (1. NRRC, CRIEPI, 2. Toshiba, 3. Hitach GE Nuclear Energy, 4. MHI)

10:30 AM - 10:45 AM

[1P03] Development of internal event (level 1) MUPRA evaluation method

(1) 内的事象（レベル1）MUPRA評価手法の検討

*Hiromichi Miura¹, Ryou Inomata¹, Kenichi Kanda¹, Tomoaki Yoshida¹ (1. CRIEPI NRRC)

10:45 AM - 11:00 AM

[1P04] Development of internal event (level 1) MUPRA evaluation method

(2) Development of inter unit Common Cause Failure evaluation method

*Ryou Inomata¹, Hiromichi Miura¹, Kenichi Kanda¹, Tomoaki Yoshida¹ (1. criepi NRRC)

11:00 AM - 11:15 AM

[1P05] Research on Dynamic PRA methodology considering dependencies of Multi-unit nuclear power plant

*Kakeru Asano¹, Akira Yamaguchi¹, Sunghyon Jang¹ (1. Univ. of Tokyo)

11:15 AM - 11:30 AM

[1P06] Development of Seismic-Tsunami PRA methodology

Part3: Quantification Process of Conditional Core Danage Probability

*Hirohisa Yamakawa¹, Hitoshi Muta¹, Yasuki Ohtori¹ (1. Tokyo City University )

11:30 AM - 11:45 AM

[1P07] Examples of PRA application to the prioritization of measures for safety enhancement at nuclear power plant

*Kenichiro Ikuno¹, Norihiro Ohara¹, Hirohisa Tanaka¹ (1. The Kansai Electric Power CO.,INC.)

Time reserved for Chair （11:45 AM - 11:55 AM）

Oral presentation

[1P08-13] Seismic Counter Measures against Cliff Edges

Wed. Sep 5, 2018 2:45 PM - 4:25 PM Room P (E21 -E Building)

Chair:Tsuyoshi Uchida(CRIEPI)

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2:45 PM - 3:00 PM

[1P08] Development of seismic counter measures against cliff edges for enhancement of comprehensive safety of nuclear power plants

Part 11 Overview

*Tsuyoshi Takada¹, Tatsuya Itoi¹, Takenori Hida¹, Hitoshi Muta², Osamu Furuya³, Keisuke Minagawa⁴, Hidemasa Yamano⁵, Akemi Nishida⁵ (1. The University of Tokyo, 2. Tokyo City University, 3. Tokyo Denki University, 4. Saitama Institute of Technology, 5. Japan Atomic Energy Agency)

3:00 PM - 3:15 PM

[1P09] Development of seismic counter measures against cliff edges for enhancement of comprehensive safety of nuclear power plants

Part 12: Classification and Definition of Required Performance against Earthquake

*Hitoshi Muta¹, Yasuki Ohtori¹, Ken Muramatsu¹, Tsuyoshi Takada², Tatsuya Itoi² (1. Tokyo City University, 2. The University of Tokyo)

3:15 PM - 3:30 PM

[1P10] Development of seismic counter measures against cliff edges for enhancement of comprehensive safety of nuclear power plants

Part 13 Identification and evaluation against cliff edges for nuclear building system

*Akemi Nishida¹, Byunghyun Choi¹, Hidemasa Yamano¹, Tsuyoshi Takada² (1. JAEA, 2. The Univ. of Tokyo)

3:30 PM - 3:45 PM

[1P11] Development of seismic counter measures against cliff edges for enhancement of comprehensive safety of nuclear power plants

Part 14: seismic counter measures against cliff edges by seismic isolation

*Keisuke Minagawa¹, Satoshi Fujita², Osamu Furuya², Tsuyoshi Takada³ (1. Saitama Institute of Technology, 2. Tokyo Denki University, 3. The University of Tokyo)

3:45 PM - 4:00 PM

[1P12] Development of seismic counter measures against cliff edges for enhancement of comprehensive safety of nuclear power plants

Part 15: Cliff-edge elimination technology for reactor vessel and piping.

*Hidemasa Yamano¹, Akemi Nishida¹, Byunghyun Choi¹, Tsuyoshi Takada² (1. JAEA, 2. Univ. of Tokyo)

4:00 PM - 4:15 PM

[1P13] Development of seismic counter measures against cliff edges for enhancement of comprehensive safety of nuclear power plants

Part 16 Modeling of Human Behavior and Evaluation of Cliff-edge

*Takenori Hida¹, Atsushi Ohno¹, Tatsuya Itoi¹, Tsuyoshi Takada¹ (1. The University of Tokyo)

Time reserved for Chair （4:15 PM - 4:25 PM）

Oral presentation

[1P14-19] Fault Displacement PRA

Wed. Sep 5, 2018 4:25 PM - 6:00 PM Room P (E21 -E Building)

Chair:Hidemasa Yamano(JAEA)

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4:25 PM - 4:40 PM

[1P14] Improvement of Fault Displacement PRA Methodology and Example of its Application to a Hypothetical NPP

(1) Outline and Examination Items

*Katsumi Ebisawa¹, Hideaki Tsutsumi¹, Toshi Sakai¹, Futoshi Tanaka², Ryusuke Haragushi², Tetsuhiro Gou², Kunihiko Sato³, Huji Nikaido⁴, Yoshinori Mihara⁴, Shinichi Yoshida⁵ (1. Central Research Institute of Electric Power Industry, 2. MHI, 3. MHI Nuclear Systems Solution Engineering, 4. Kajima, 5. Obayashi)

4:40 PM - 4:55 PM

[1P15] Improvement of Fault Displacement PRA Methodology and Example of its Application to a Hypothetical NPP

(2) Example of Evaluation for Improving Evaluation Position of Fault Displacement Hazard

*hideaki tsutsumi¹, sakai toshiaki¹, yuyama ayumi¹, ebisawa katsumi¹, mihara yoshinori², nikaido yuji², haraguchi ryusuke³ (1. Central Research Institute of Electroric Power Indutry, 2. kajima Copration, 3. Mitsubishi Heavy Industries)

4:55 PM - 5:10 PM

[1P16] Improvement of Fault Displacement PRA Methodology and Example of its Application to a Hypothetical NPP

(3) Validation Case Study of Fault Displacement Fragility Evaluation Methodology

*Yuji Nikaido¹, Yoshinori Mihara¹, Hideaki Tsutsumi², Ayumi Yuyama², Toshiro Sakai², Katsumi Ebisawa², Ryusuke Haraguchi³ (1. Kajima Corporation, 2. CRIEPI, 3. Mitsubishi Heavy Industry)

5:10 PM - 5:25 PM

[1P17] Improvement of Fault Displacement PRA Methodology and Example of its Application to a Hypothetical NPP

(4) Example of Application of Fault Displacement Accident Scenario Identification and Accident Sequence Evaluation Methodology to a Hypothetical NPP

*Futoshi Tanaka¹, Manabu Miyata¹, Ryusuke Haraguchi¹, Kunihiko Sato⁴, Shinichi Yoshida³, Hideaki Tsutsumi², Toshiaki Sakai², Katsumi Ebisawa² (1. MHI, 2. CRIEPI, 3. Obayashi, 4. MHINSS)

5:25 PM - 5:40 PM

[1P18] Improvement of Fault Displacement PRA Methodology and Example of its Application to a Hypothetical NPP

(5) Example of Application of Fault Displacement Fragility Evaluation Methodology to a Hypothetical NPP

*Ryusuke Haraguchi¹, Tetsuhiro Gou¹, Kunihiko Sato², Shinichi Yoshida³, Hideaki Tsutsumi⁴, Toshiaki Sakai⁴, Katsumi Ebisawa⁴ (1. Mitsubishi Heavy Industries, LTD., 2. MHI Nuclear Systems And Solution Engineering Co., Ltd, 3. OBAYASHI Corp., 4. Central Research Institute of Electric Power Industry)

5:40 PM - 5:55 PM

[1P19] Investigation and Consideration about Risk Evaluation by Fault Displacements for Nuclear Facilities(2)

-The Efforts both in Japan and Other Countries, and The Research Activities of JAPC-

*Masanobu Kamiya¹, Kouichi Kamiya¹, Tsutomu Ogawa¹ (1. JAPC)

Time reserved for Chair （5:55 PM - 6:00 PM）

Sessions

IV. Nuclear Plant Technologies » 403-1 Risk Assessment Technology, Application of Risk Information

[2O01-05] Plant PRA

(1) Issues Based on Internal Events At-Power Level 1PRA Upgrade

(1) Issues Based on Internal Events At-Power Level1 PRA Upgrade

(2)Extraction of Initiating event candidate "Implementation of failure mode effect analysis"

(5)Evaluation Results of Level 1.5PRA During Power Operation Considering SA Equipment

(6)Development of Core Damage Monitoring Tool During Power Operation(Level1 PRA)

[2O06-09] PRA Improvement

(9) Applicability study of the Source Term PRD to the ADAPT method

(10) Consideration of Source term PRD method for a variety of scenarios expected in the SBO scenario

(11)Evaluation of cesium re-evaporation amount depending on dispersion state of molten debris in containment vessel.

[2O10-11] PRA Application

Part 1: STAMP Model for External Events

[1P01-07] PRA Methodology

(1) 内的事象（レベル1）MUPRA評価手法の検討

(2) Development of inter unit Common Cause Failure evaluation method

Part3: Quantification Process of Conditional Core Danage Probability

[1P08-13] Seismic Counter Measures against Cliff Edges

Part 11 Overview

Part 12: Classification and Definition of Required Performance against Earthquake

Part 13 Identification and evaluation against cliff edges for nuclear building system

Part 14: seismic counter measures against cliff edges by seismic isolation

Part 15: Cliff-edge elimination technology for reactor vessel and piping.

Part 16 Modeling of Human Behavior and Evaluation of Cliff-edge

[1P14-19] Fault Displacement PRA

(1) Outline and Examination Items

(2) Example of Evaluation for Improving Evaluation Position of Fault Displacement Hazard

(3) Validation Case Study of Fault Displacement Fragility Evaluation Methodology

(4) Example of Application of Fault Displacement Accident Scenario Identification and Accident Sequence Evaluation Methodology to a Hypothetical NPP

(5) Example of Application of Fault Displacement Fragility Evaluation Methodology to a Hypothetical NPP

-The Efforts both in Japan and Other Countries, and The Research Activities of JAPC-

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