overview of regulations and guides in japan · overview of regulations and guides in japan iaea,...
Post on 29-Dec-2019
8 Views
Preview:
TRANSCRIPT
Tsuyoshi Nakajima Regulatory Standards and Research Division Nuclear Regulation Authority (NRA-Japan)
Overview of Regulations and Guides in Japan
IAEA, Vienna, Austria 3-6 October 2016
Technical Meeting on Novel Design and Safety Principles of NPPs
Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
Contents
i. Japan Update
ii. Overview of the New Regulation
iii. Practical Elimination and Safety Goal
iv. Review Guide for Severe Accident Measures
v. Continuous Improvement for Safety
vi. Conclusions
1 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
i. Japan Update
2 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
Timeline and Current Status
The NRA was established in Sep. 2012 and urgently started developing the new regulatory requirements for NPPs which came into force in July 2013.
After the 1F accidents, all the 48 units had suspended their operation one by one by May 2012.
• 26 units (16 PWRs, 10 BWRs) have applied for conformance review to the new requirements
• NRA has granted the permissions for 7 units: Sendai-1, -2, Takahama-1~-4 and Ikata-3
• Sendai-1, 2 and Ikata-3 in operation
IPPAS mission’s review was done in Feb. 2015
IRRS mission’s review was done in Jan. 2016
3 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
Nuclear Power Reactors in Japan
<Tomari>
<Higashidori>
<Onagawa>
<Fukushima Dai-ichi>
<Fukushima Dai-ni>
<Tokai Plant, Tokai Dai-ni>
<Hamaoka>
<Ikata>
<Sendai >
<Genkai >
<Shimane >
<Takahama>
<Ohi >
<Kashiwazaki-Kariwa>
<Shika>
<Mihama>
<Tsuruga>
Reactors undergoing decommissioning (3)
Already Service Terminated (6)
Specified nuclear facility
BWR (24)
PWR (24)
Restarted (3)
Applied (26)
<Ohma> BWR, under Construction (2)
As of Oct, 2016
Application
PWR 16
BWR 10
Total 26
Application of Conformity Review for NPPs
4 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
Licensee Facility
JNFL Reprocessing /Uranium Enrichment /MOX Fuel Fab。/High-Level Radioactive Waste Storage Center
RFS Spent Fuel Storage Facility (Interim Storage)
JAEA Oarai R&D Center (Waste Management Facility)
MNF Uranium Fuel Fab. Facility (PWR)
NFI Uranium Fuel Fab. Facility (Tokai(BWR)/Kumatori(PWR))
GNF-Japan Uranium Fuel Fab. Facility (BWR)
Kyoto Univ. RRs (KUR/KUCA)
Kinki Univ. RR
JAEA RRs(JRR-3/NSRR), STACY , R&D facility
JAEA Oarai R&D Center, RRs (HTTR/JMTR)
Application of Conformity Review for FCFs and RRs
5 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
ii. Overview of the New Regulations
6 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
Revision of the Reactor Regulation Act Overview
1. NRA can issue rules and permissions as the RB
2. Back-fit system: No difference from new and existing NPPs Moratorium may be decided when the additional
requirement established Specialized Safety Facility …… 5 years moratorium
3. Clarification of the Primary Responsibilities for operators
4. Evaluations to improve the safety of NPPs: Periodically Update as FSAR’
5. Limits on the operation period: 40 years only one extension up to 20 years if approved by the NRA
7 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
<Previous>
<New>
Re
info
rced
&
Ne
w
(SA M
easu
res)
NEW
R
ein
force
d
Req. for AOOs and DBAs were strengthened.
Req. for “SAs” that are equivalent to “DECs” in SSR 2/1 were newly added.
DiD4
Structure of New Regulatory Requirements
8 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
Seismic / Tsunami resistance
Natural phenomena
Reliability of power supply
Function of other SSCs*
Fire protection
Seismic / Tsunami resistance
Natural phenomena (Volcano, Tornadoes, Forest fire: New)
Prevention of core damage (Postulate multiple failures)
Suppression of radioactive materials dispersal
Response to intentional aircraft crash
Prevention of CV failure & large release
Function of other SSCs
Internal flooding (New)
Fire protection
Reliability of power supply DiD3
iii. Practical Elimination and Safety Goal
9 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
The New Requirements in Plant States
New Design Requirements
Previous Design Requirements
Operational States Accident Conditions Practically
Elimin
ated
o
f Early/Large
Re
lease
NO AOO DBA DEC
w/o Sig. Fuel Deg. (DEC-a)
w/Core Melt (DEC-b)
1 2 3 4a 4b
Non-P.E.: SFP, Catastrophic Disaster, Intentional Aircraft Crash B-DEC: Mobile equipment, e.g. Cannon Spray Pump DEC Mitigation Equip.: Classified in Higher Class SSR-2/1 (Rev. 1): No Significant Gaps
Operating Safety Program (~EOP~SAMG~)
Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016 10
Safety Goal (Conceptual Scheme)
CDF CFF-1 CFF-2
Status
Freq. 10-4 10-5 10-6
Release 100 TBq (CS137)
Measures Prevent Core
Damage Prevent CV Failure Prevent CV Damage
& Large Release Mitigate
Expansion
Core Damage Controlled Release Uncontrolled Release
Applied to all NPPs equally
Safety Goal is the goal that NRA should achieve through implementing its regulation over nuclear facilities
Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016 11
iv. Review Guide for Severe Accident Measures
12 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
1. Outline of SA Measures Requirements
General Requirements on the SA measures Equip.
Preparation of procedures, implementation of drills, and development of organizational system
Prepare equipment and procedures for the following 19
Outline of SA Measures Requirements
13 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
Prepare equipment and procedures
14 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
Reactor shutdown Cooling reactor at high / √ low pressure Depressurizing RCPB Securing UHS Cooling, depressurization and RM reduction in the atm. CV Preventing the CV failure due to overpressurization Cooling molten core fallen to the bottom of the CV Hydrogen explosions inside the CV and R/B etc. Cooling, shielding and maintaining the sub-criticality of SFP Securing make-up water and water sources √power sources Control room √Emergency response center Instrumentation devices Radiation monitoring facilities Communications devices Suppression of off-site radioactive
2. AM for External Events beyond Design Basis
AM with mobile equipment, etc.
3. Evaluation of the Effectiveness of SA Measures
Preventive measures against core damage and CV failure
Prevent measures against fuel damage in SFPs
Prevent measures against fuel damage in a reactor during shutdown
AM for EE beyond DB & Evaluation
15 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
v. Continuous Improvement for Safety
16 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
1. “As-Built” or “As-Is” plant description and compliance with requirements (Clarification of “license basis”)
2. Voluntary Efforts for Safety Improvement: Policy and plan on continuous improvement of safety
Feedback of operating experience and state-of-the-art knowledge/information, and plant walk-down
Additional actions taken
Peer Review (e.g. IAEA OSART)
3. Effectiveness of voluntary efforts demonstrated by: Level 1 and 2 PRAs for both internal / external events
Safety margin analysis (e.g. stress test)
4. Comprehensive Assessment for Plant Safety
Continuous Improvement of Regulatory Requirements and Systems
17 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
Continuous Improvement of Regulatory Requirements and Systems
1. Strengthen the OEF Process through “Technical Information Committee” • “Single-Phase Open Circuit” (Byron-2, US, 1/2012), ⇒Amended a relevant regulatory guide.
2. Always be vigilant to the state-of-the-art knowledge / information and therefore, is enhancing its learning process through bilateral / multilateral international cooperative activities.
18 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
Secretariat of NRA: • Collection and Analysis of OE and
Regulatory Activities • Screening” and Tracking” • Communication with Licensees
• Actions: “Information notice” to Licensees New Regulations and Guides Amendments to Existing Rs & Gs
NRA’s System for Global OEF
Advisory Committees
Technical Information Committee
Information Sources: • OECD/NEA, IAEA IRS,
FINAS, INES,… • OECD/NEA/CNRA WGOE,
WGIP, IAEA IRS,..
• IAEA CSS, INSAG, IEMs,.. • OECD/NEA CSNI • Public information:
• U.S.NRC’s Bulletins, Generic Letters, Info. Notices
• Bilateral info. exchange
The NRA
Licensees
19 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
vi. Conclusions
20 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
Conclusions
• The New Safety Requirements have been enforced since July, 2013 taking into account L.L. from 1F Accidents and IAEA SSs, such as …
Introduced DiD with Independency among levels …… Practically
Use of non-permanent equipment Back-fit rule Safety Margins by stress test
• Main Points are ………
SAM for Conditions exceeding DiD level 4 Higher value of the DBE for DEC equipment Improve safety continuously
21 Technical Meeting on Novel Design and Safety Principles of NPPs, Vienna, Austria, 3-6, October, 2016
top related