Technical support activities of SNERDI during the first ... · first application of NPP Operational License ... 2.Fatigue Analysis of Reactor Pressure Vessel ... Low Shell 0.02157

©SPIC 2017. All Rights Reserved.

Technical support activities of SNERDI during the

first application of NPP Operational License

Extension in China

Zhenhui Han, Yikang Dou

Shanghai Nuclear Engineering Research & Design Institute, China

上海核工程研究设计院有限公司www.snerdi.com.cn

Fourth International Conference on

Nuclear Power Plant Life Management

23-27 Oct. 2017, Lyon, France


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without the prior written permission of SPIC.


Contents

� Background of SNERDI, Qinshan phase-I and OLE

� OLE application of NPP in China

� Technical support activities of SNERDI

� Conclusions

� Background of SNERDI, Qinshan phase-I and OLE

� OLE application of NPP in China

� Technical support activities of SNERDI

� Conclusions


Background of SNERDI, Qinshan Phase-I and OLE

� Established on Feb. 8, 1970, SNERDI was the designer of Qinshan

Phase-I 320MWe NPP, the 1st NPP in China, from where nuclear

industry was established.

� SNERDI became a subsidiary of SNPTC since 2007( from CNNC).


Background of SNERDI, Qinshan Phase-I and OLE

� The design lifetime of Qinshan Phase-I is 30 years. It has been in

safe operation for near 26 years since Dec. 15,1991.

� The preparation for application for life extension of Qinshan Phase-I

plant has started from 2011.

� Although nuclear safety requirements and guidelines for life

extension have not been established, the preparation to establish

license system is ongoing.

� In China, life extension is called Operation License Extension (OLE)


OLE application of NPP in China

� In end of 2015, NNSA issued “Technical Policies of NPP

Operational license valid period extension (Trail)”

� The OLE application should be submitted 5 years before the

expiry of the operational license.

� Maximum 20 years extension of operation license once a time.

� Review of OLE application will based on the license basis when

approved for operation plus supplemental safety requirements

during operation.

� Besides Chinese nuclear safety regulatory documents, some

international guidance or practice may be applicable.


OLE application of NPP in China

� The application should be submitted along with the reports on

� Integrated plant assessment (IPA) report based on aging

management review (AMR) of the SSCs in the scope of OLE

application

� Series of TLAA reports of the identified SCs

� Safety assessment reports for SSCs refurbishment

selected from PSR results

� Addendum of environmental impact assessment report.

� Addendum and revised FSAR.

� In end of 2015, NNSA issued “Technical Policies of NPP

Operational license valid period extension (Trail)”


Technical support activities of SNERDI

2013 2014 2015 2017 2020 20212016

R18（2018.4～2019.4） R19、R20

2021.12获得延照运行执照OLE

permission

制定技改总体计划Integrated schedule

establishment

Main Schedule for Qinshan-1 OLE



Main Task of Qinshan Phase-I OLE application

� AMR & IPA

� AMP Modification, Implementation Plans Establish and Follow up

Activities

� TLAAs

Metal Fatigue

RPV

I&C Equipment EQ

others of plant specific TLAAs

� Environmental impact assessment

� FSAR supplement analysis

� Engineering renovation and system modification



（1） Applicability review for the change in properties

after irradiation of RPV

A total of six RPV irradiation surveillance capsules of Qinshan

Phase-I 320MWe plant has been withdrawal and the specimens inside

have been tested. The tensile properties, fracture toughness and impact

properties for RPV materials have been reviewed.

Conclusion:

Up to now, the change of the properties of Qinshan 320MWe plant

RPV is quite normal.

1. Reactor Pressure Vessel Neutron Embrittlement



（2）Charpy Upper-Shelf Energy (USE)

The Charpy upper-shelf energy of the RPV material should always

be maintained at 68 J (50 ft-lb) or more during the entire plant life.

USE of QS1 WeldsUSE of QS1 Base Metal





（3）Adjusted Reference Temperature (50 years)

R.G 1.99（1988）

MethodCF /℃ M /℃

∆RTNDT /℃ ART /℃

3/4T 1/4T 3/4T 1/4T

Base

Guideline

recommended17.22 26.71 20.10 23.54 26.81 30.26

Radiation

monitoring23.80 21.12 27.78 32.53 28.90 33.65

Weld

Guideline

recommended37.78 36.40 18.02 25.48 34.41 41.88

Radiation

monitoring10.04 24.47 4.79 6.77 9.26 11.24



MAR 17 2016

2. Fatigue Analysis of Reactor Pressure Vessel



2. Fatigue Analysis of Reactor Pressure Vessel

ComponentCumulative Fatigue Usage Factor

LimitInside Outside

Closure Head 0.06760 0.01920

1

Closure Stud 0.11704 0.24592

Stud Hole 0.37509 0.37509

Low Shell 0.02157 0.04009

Low Head 0.00992 0.01006

Bracket 0.32198 0.29208

Inlet Nozzle 0.03331 0.00942

Outlet Nozzle 0.02093 0.00847

Safe End 0.00570 0.00924

Instrumentation Nozzle 0.00581 0.00917

CRDM Adapter 0.00842 0.26790



3. Fatigue Analysis of Steam Generator

primary nozzle primary manway

tubesheet, and lower shell complextransition cone and upper shell

� FEA Models



feedwater nozzle

Steam Outlet Nozzle

tubes

� FEA Models





Components Maximum Fatigue Usage Limit Location

Primary Nozzle 0.17949 1 ASN2 Inside

Primary Manway 0.19201 1 ASN2 Inside

Tubesheet and lower shell

complex0.31875 1 ASN6 Inside

Transition cone and upper

shel0.01428 1 ASN8 Outside

Feedwater Nozzle0.43657 1

ASN16 Inside

Steam Outlet Nozzle0.01565 1

ASN6 Inside

Tubes 0.48322 1 AA Outside



4. Environmental Impact Assessment



4. Environmental Impact Assessment

• the appropriateness of <NPP Environmental Impact Report>(operation phase)

Environmental impact of NPP since operation conforms to the

conclusion of <NPP Environmental Impact Report>(operation phase).

The environmental impact is acceptable.

• the acceptance of environmental impact from the operating extension of NPP

Environmental impact from the operating extension of NPP is acceptable.



5. Update of FSAR

FSAR revision work requirements:（1）Determine the OLE evaluation basis：According to plant actual state before OLE to revise FSAR as basis, including law, regulatory, standard complied or referred during NPP design, construction or operation.

� Ten Years Periodic Review (PSR): SSCs modifications or the standard version upgrade

� Other safety modifications approved by National Nuclear Safety Administration

（2）Submit FSAR supplement and revision� It should include summary description of Ageing

Management Program ,Ageing Management review and Time-limited aging analysis.

� According to aging effect requirement of license extension to revise Technical Specification.



� Regularly maintain and update the FSAR supplementary report

and the modification list

� OLE evaluation review comments

� Review and modification based on site environmental

parameter change

� Engineering Modification

� The 2rd PSAR vulnerabilities improvement

� FSAR re-revise

� Renew FSAR according to modification list

5. Update of FSAR


Conclusions

1）The first OLE project of Chinese NPPs, i.e. Qinshan Phase-I plant, has a

big progress, either on regulatory side and on utilities side.

2）SNERDI assisted owner to carry out OLE-related feasibility study,

collecting and determining license basis for OLE application, to sort out the

initial screening of OLE safety evaluation benchmarks, aging management

and OLE safety evaluation, a number of important TLAAs work;

3）SNERDI assisted utility to carry out OLE environmental impact

assessment work and preparation of environmental reports, and also FSAR

update analysis;

4）Finally, based on the results of the previous two periodic safety reviews

(PSR) of the plant, SNERDI provided comprehensive technical support for

important system modifications and related safety analysis that have been

implemented to further enhancement of safety during the operation of the

nuclear power plant.


谢谢！THANKS FOR YOUR ATTENTION ！

上海核工程研究设计院有限公司www.snerdi.com.cn

Technical support activities of SNERDI during the first ... · first application of NPP Operational License ... 2.Fatigue Analysis of Reactor Pressure Vessel ... Low Shell 0.02157

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