improvement of tepco’s alara process
DESCRIPTION
Improvement of TEPCO’s ALARA Process. Shiro TAKAHIRA Tokyo Electric Power Company Radiation Protection Group ISOE-ATC Symposium October 12 , 2006 , Yuzawa, Niigata-pref., Japan. Contents. TEPCO situations Exposure trends ALARA activities Improvement of Process Objectives and Approach - PowerPoint PPT PresentationTRANSCRIPT
Improvement of TEPCO’s ALARA Process
Shiro TAKAHIRATokyo Electric Power Company
Radiation Protection Group
ISOE-ATC Symposium
October 12, 2006, Yuzawa, Niigata-pref., Japan
Contents
• TEPCO situations– Exposure trends– ALARA activities
• Improvement of Process– Objectives and Approach– Identifying gaps– Scope of Activities
• Improved Process– Mid-/long-term dose target process– Outage dose target process
Profile - Location
TEPCO’s Nuclear Power Plants
17 BWRs including 2 ABWRs (total capacity 17,308MWe) - 28% of generation capacity - 33% of generated electricity (FY 2004)
TEPCO’s Nuclear Power PlantsUnit Type Capacity
(MW)
CommercialOperation Start
No.1 BWR-3 460 Mar.1971No.2 BWR-4 784 Jul.1974No.3 BWR-4 784 Mar.1976No.4 BWR-4 784 Oct.1978No.5 BWR-4 784 Apr.1978No.6 BWR-5 1100 Oct.1979No.1 BWR-5 1100 Apr.1982No.2 BWR-5 1100 Feb.1984No.3 BWR-5 1100 Jun.1985No.4 BWR-5 1100 Aug.1987No.1 BWR-5 1100 Sep.1985No.2 BWR-5 1100 Sep.1990No.3 BWR-5 1100 Aug.1993No.4 BWR-5 1100 Aug.1994No.5 BWR-5 1100 Apr.1990No.6 ABWR 1356 Nov.1996No.7 ABWR 1356 Jun.1997
FukushimaDaiichi(1F)
FukushimaDaini(2F)
KashiwazakiKariwa(KK)
Exposure Trends in TEPCOPerson-Sv No. of Person
Fukushima Daiichi NPS
Fukushima Daini NPS
Kashiwazaki Kariwa NPS
0
20
40
60
80
100
70 75 80 85 90 95 00 05Fical Year
Occ
upat
iona
l Dos
e (P
erso
n-Sv)
0
3,000
6,000
9,000
12,000
15,000
Num
ber
of w
orke
rs
TEPCO’S ALARA Activities• Radiation Field Control
– Source term removal • Reduced corrosion products from feed water piping by
injecting oxygen
• Use of low-cobalt material
• Use of weatherproof steel in component materials for feed water and condensate system
• Dual condensate purification system
• Flushing and Chemical Decon.
– Shielding • Permanent shielding in PCV• Temporary shielding for high-radiation work
• ALARA Management
Annual Collective Dose
0
1
2
3
4
5
6
7
8
9
10
'80 '81 '82 '83 '84 '85 '86 '87 '88 '89 '90 '91 '92 '93 '94 '95 '96 '97 '98 '99 '00 '01 '02 '03 '04
Year
Per
son
-Sv
J apan USA Sweden Spain Finland France Korea
Collective Dose in FY2005
(Person-Sv/yr・ reactor)
Fukushima Daiichi (1F)
2.6
Fukushima Daini (2F) 1.1
Kashiwazaki Kariwa (KK)
1.3
Benchmarking
Collective Dose in BWR 2003-2005 Average( )
0.0
0.5
1.0
1.5
2.0
2.5
3.0
3.5
4.0
4.5
Tar
apur
Per
ry
Fuku
shim
a D
aiic
hi(6
)
Tok
ai-I
I
Qua
d C
ities
(2)
Cof
rent
es
Lagu
na V
erde
(2)
Nin
e M
ile P
oint
(2)
Rin
ghal
s
Bro
wns
Fer
ry(2
)
Col
umbi
a G
en S
ta
Ham
aoka
(4)
LaSal
le(2
)
Shi
man
e(2)
Tsu
ruga
Kuo
shen
g(2)
Fuku
shim
a D
aini
(4)
Dre
sden
(2)
Riv
er B
end(
1)
Pilg
rim(1
)
Shi
ka
Ver
mon
t Yan
kee
Pea
ch B
otto
m(2
)
Coo
per
(1)
Kas
hiw
azak
i Kar
iwa(
7)
Hop
e C
reek
Bru
nsw
ick
(2)
Gun
drem
min
gen
Npp
(2)
Chi
nsha
n(2)
Mon
ticel
lo
Clin
ton
Ferm
i
Gra
nd G
ulf
Mue
hleb
erg
Bru
nsbu
ette
l
Sus
queh
anna
(2)
Leib
stad
t
Fitz
Pat
rick
Kru
emm
el
Phi
lipps
burg
Oys
ter
Cre
ek
Dua
ne A
rnol
d
Hat
ch(2
)
San
ta M
aria
De
Gar
ona
Lim
eric
k (2
)
Isar
Osk
arsh
amn(
3)
Olk
iluot
o(2)
Fors
mar
k(3)
Ona
gaw
a(3)
Col
lect
ive
Dos
ePer
son-
(yr
reac
tor
)(
Sv/
・)
Top Quartile2nd Quartile3rd QuartileBottom Quartile
Objectives • Reshape ALARA Management by;
– Reviewing ALARA management “As-Is” process– Identifying a gap between “As-Is” and “To-Be”
process– Focusing on the interface between radiation
protection and maintenance staff at work planning and post-outage steps
Incorporating ALARA Considerations into Job
More Efficiently and Effectively!
• The project team “Dose Target Control Peer Team” organized
• Team Members– Leader : Radiation Protection Manager(H/O)– Permanent Members : Radiation Protection,
Radiation Safety, Chemistry staff from H/O , 1F, 2F, KK
– Temporary Members: Maintenance staff from H/O,1F, 2F, KK
Approach
Identifying Gaps
• Lack of mid- and long-term target
• Lack of inter-group communication between RP and maintenance group– Little RP staff involvement of work planning
and post-job performance review – Little chance to identify good practice and
to propose dose reduction measures for job
Lack of Mid- / Long-term Target
Vision
Expectations from the management(Division Director,Site President)
Projection of :•Each work dose•Outage dose•Annual dose
Mid- and Long-term Dose Plan
Lack of Interface
Annual dose plans
RWA Review / approval
Outage dose plan
Tracking dose
RWA report
Outage report
Long-term plan
Outage plan
Review detailed work schedule
Work management
Post-outage follow-up
Incorporation of lessons learned
Review main work schedule
Maintenance RP
Weak Relations
Weak Relations
Team Vision
The Dose Target Control Peer Team facilitates
the Maintenance Department and Radiation
Control Department as they jointly define
provisions to be implemented in each step of
maintenance processes(planning, scheduling,
work and evaluation), and communicate with
each other to evaluate planned and actual
figures in dose targets, thereby achieving dose
reduction.
Scope of Activities
Setting Outage Dose Target Process
Planning
Work
Check&Review
Follow-up Action
Setting Mid- and Long-term Dose Target Process Proposal for incorporating
dose reduction measures
Reviewing dose performance
Examining reflection items
for the next outage
Basic Policy for Mid- and Long-term Exposure
Reduction
Dose Target Plans for annual and Mid- /Long-term Exposure
Reduction
Maintenance
Process
Radiation Protection Management
Setting Mid- / Long-term Plans
Expectedperformance
Projected performance
The world’s top 25%
The world’s top XX%
The world’s top AA%
Mid- / Long-term and Annual Dose
plans
Basic Policy
out
pu
t
input
Future schedule
Past performance
input
input
New processNew process
Expectations
Vision of site doseperformance
Basic Policy
• Proposed by Radiation Protection & Management Group (head office)
• Approval of director of nuclear power plant management department(head office)
• Annually assess implementation results and determine the need for review
Ex.)World BWR’s top quartile of exposure reduction performance
Mid- / Long-term and Annual Dose Plans
• Proposed by Radiation Safety Group (Site)
• Approval of Site President
• Annually review
• Site president assesses “projected performance” by comparing with “expected performance”, and decides “vision of site dose performance”.
Interface between Maintenance and RP
Mid- /Long-term andMid- /Long-term and annual dose plansannual dose plans
RWA Review / approval
Outage dose plan
Tracking dose
RWA report
Outage reportOutage report
RP proposalRP proposal
Involved in work scheduleInvolved in work schedule
Long-term plan
Outage plan
Review detailed work schedule
Work management
Post-outage follow-up
Incorporation of lessons learned
Review main work schedule
Maintenance RP
RP Proposal
• Proposed dose reduction measures to maintenance team before outage contract
• RP Proposal– Effecting long-term or short-term(outage)
maintenance plans– For selected job (High radiation work)– Based on lessons learned at former outage
Involvement in Work Schedule• RP share information of detailed work
schedule with maintenance team and contractors.
• RP involvement– Suggestions for rearranging the work steps
which achieve significant dose reduction.– Providing dose information of the same
operation areas to maintenance team and contractors (Each job process optimally planned from the perspective of dose reduction).
Outage Report• Prepared by RP at post-outage follow-
up step and report out to maintenance team
• Including what maintenance team expect to know about outage jobs
• Involving following information – Dose performance of selected jobs– Proposals for dose reduction measures
that should be reflected to the next outage or other plants
– Punch lists for the proposal.
Implementation Program
• Mid- and long-term dose target process– Beyond FY 2007– Identifying site goal(slogan and target
value)• (ex.)World’s Top quartile at 20XX which means
yearly 1 person-Sv per reactor
– Draft document of basic policy and mid-/long-tern dose plan in this year
Process performance evaluated after implementation
Implementation Program• Outage dose target process
– Trial implementations this year– One or two plants of each stations for the
trial– Selected a couple of high radiation jobs of
each trial plants– Trial implementation identify validity of
process and issues before the start of full implementation
Process performance evaluated after trial implementation
SummaryExpected effects of process improvement ;• Setting “targets” in the basic policy as well
as mid/long-term and annual plans, will clarify the expectation of the management and the vision of exposure reduction.
• RP can provide more suggestions or feedbacks to the maintenance personnel in the outage dose target process by enhancing communications, then ALARA activities goes more effectively and efficiently.