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CCTV System for Radiation Work Management
Yonggwang NPP Unit 5 & 6
Contents
Ⅰ. YGN Unit 5 & 6
Ⅱ. Brief Overview of Radiation Protection
Ⅲ. Description of CCTV system
Ⅳ. Cases for use of CCTV system
Ⅴ. Effects
Ⅵ. IAEA OSART Good Practice
Ⅶ. Conclusion
Type : PWR Power Level : 1,050MWe 2 Loops, 2 S/Gs, 4 RCPs 177 Fuel Assy’s, 16 × 16 tubes S/G : Vertical U-tube with
Economizer Condenser Heat Sink : Sea water
□ Key Features
Ⅰ. YGN Unit 5 & 6
Ⅱ. Brief Overview of Radiation protection
□ Statutory Exposure Dose limit
Category Workers Frequent Visitors General Public
Effective Dose Limit 100mSv per 5 years 12mSv per year 1mSv per year
□ Site Exposure Dose limit
Category Workers Frequent Visitors General Public
Effective Dose Limit 16 mSv per year 10 mSv per year 1 mSv per year
Ⅱ. Brief Overview of Radiation protection [cont’d]
□ Radiation Work Control
Anticipated Exposure (man-mSv) Counter plan
< 10 Review and check work order
10 ~ 70 Work Order Approval
70 ~ 200 ALARA Acting Level Committee Review
> 200 ALARA Committee review
□ Collective Radiation Exposure
Ⅱ. Brief Overview of Radiation protection [cont’d]
Year
Ⅲ. Description of CCTV system
□ Purpose
Radiation Exposure Reduction
Efficient Radiation Safety Control in RCA
Continuous Check-up for important works and
facilities integrity
□ Characteristics Real-time information by LAN
Movable Cameras can support important or high
radiation work anywhere
Ⅲ. Description of CCTV system [cont’d]
□ Composition
Item # 5 # 6 RWB
Monitoring System 1 Set 1 Set -
Announcement System 1 Set 1 Set -
CameraFixed 7 Sets 7 Sets 4 Sets
Movable 2 Sets 2 Sets -
Data Cable 3.3 Km 3.3 Km 1.1 Km
Movable or Fixed
OfficeLobby Monitor
HP RoomConsole Lack
LAN LAN
Ⅲ. Description of CCTV system [cont’d]
□ Network
Building Elevation Location Details Main Function
ACB100 Locker Room Area Prevention of robbery
100 Entrance to RCA Check-up personnel coming in and out
SAB100 General Access Area “
77 General Access Area ″
FHB100 Truck Bay Area Check up entry and exit of equipment and person
142 Storage Area ″
PAB 144 Personal Airlock Area Controlling entry and exit in high radiation area
RWB
100 Hot Machine Shop Check-up personnel coming in and out
100 Entrance of RCA Controlling entry and exit in high radiation area
100 Truck Bay Area Check-up entry and exit of equipment and person
70 Access Area Check-up personnel coming in and out
Ⅲ. Description of CCTV system [cont’d]
□ Location (Fixed Camera)
Building ElevationNumber of
jacksMain Function
RCB
100 2 Installation and removal of SG Nozzle dam Installation and removal of SG man-way ECT (Eddy current test)
125 2 Maintenance of RCP and related works Lancing and FOSAR in secondary side of SG
142 2 Reactor Maintenance fuel loading and withdrawal Check-up entry and exit of equipment and person
Ⅲ. Description of CCTV system [cont’d]
□ Location (Movable Camera) Movable Cameras are communicated with main control center by using connecting jack
Ⅲ. Description of CCTV system [cont’d]
□ View of Fixed Camera
Ⅲ. Description of CCTV system [cont’d]
□ View of Movable Camera
Ⅲ. Description of CCTV system [cont’d]
□ CCTV system Diagram
PAB 144’
HP ROOM
ACB 100’LOCKER AREA ROOM
ACB 100’ Entrance of RCA
SAB 100’ GEN ACCESS AREA
SAB 77’ GEN ACCESS AREA
FHB 100’ TRUCK BAY AREA
FHB 142’ STORAGE AREA
PAB 144’ PERSONAL AIRLOCK AREA
LINK FACILITY
MATRIXSWITCHER
MONITORINGSERVER(DVR)
KEYBOARDKEYBOARD
MONITORMONITOR
to RWB
4SET
11SET
LINK FACILITY
Ⅲ. Description of CCTV system [cont’d]
□ HP Room Console Rack (Main control center) Real time Monitoring all places
where cameras are located.
Recording important works
Announcing
Auto Recording when any movement is detected.
Ⅲ. Description of CCTV system [cont’d]
□ Monitoring in HP Room Console Rack
All locations under surveillance The main work place
□ Comparison (use or not)
Ⅲ. Description of CCTV system [cont’d]
Work Year Number of workers
WorkingTime (man-hr)
Exposure Dose (man-mSv)
CCTV use or not
SG Nozzle Dam
2003 61 101 11.02 Not
2006 52 62 6.30 Use
ECT2003 435 1,044 38.3 Not
2006 290 698 23.41 Use
SG Man-way
2003 83 156 6.23 Not
2006 81 177 4.33 Use
Ⅳ. Cases for use of CCTV system
□ Removal of remaining Thermal Sleeve (T/S)
2005.05 Unit 5 third Planned Outage (37 days)
Case 1
During the first outage of unit 5, a metal object was discovered in
the Reactor Bottom Head. (conformed by Remote Video Inspection)
As a result of the specific inspection, three metal objects were
discovered. These objects have been identified as missing thermal
sleeves from the Safety Injection Nozzle.
A remaining T/S was planned to be removed during the third Outage
<Related event description>
Ⅳ. Cases for use of CCTV system
Material : Inconel 690Size (mm) : 304(W)×554(H)×4.5(T)Weight (kg) : 20KgDose rate (removal): 6mSv/hr
Ⅳ. Cases for use of CCTV system [cont’d]
□ Monitoring T/S Work through CCTV System
Ⅳ. Cases for use of CCTV system [cont’d]
□ Result of ALARA ControlTarget (mSv) Result (mSv) %
Dose 160 73.91 53.8
Reason of exposure Reduction
Content Reduction Rate(%)
Work control (Lead shielding and vest) 10
Reduction of the Number of person( Effect of CCTV) 10
Optimization of Working time (Effect of CCTV) 6
Cancellation of some work 28.8
SUM 53.8
Ⅳ. Cases for use of CCTV system [cont’d]
□ Effect of using CCTV System
Reduction of Exposure : 16 man-mSv (10%) About 15 persons supervised the work through CCTV
during the working period (11days)
= persons x staying time x Radiation level in the area
Optimization of Working Time : 9.6 man-mSv (6%)
Reduction of Radioactive Waste : 1 Drum
About 220 pairs of Rubber gloves / paper protection Clothes
Ⅳ. Cases for use of CCTV system [cont’d]
□ Maintenance of leak Valve (SI-V522) in SI System Date : ’07. 7.17(unit 6 fourth outage) Work Description
• At the time of NOT/NOP, SI- check Valve 522 of High Presser
Safety injection Header leaked
• Piping was isolated throughout Ice plugging and Valve was
Maintained
• CCTV System was used to monitor the maintenance work
and ALARA Control
Case 2
Ⅳ. Cases for use of CCTV system [cont’d]
□ Result of ALARA Control
Target (mSv) Result (mSv) %
Dose 6.69 5.75 14
Number of workers : 16 Total working time : 6 hrs
Ⅴ. Effects
Reduction of the number of person coming in and out
Reduction of exposure dosage
Reduction of radioactive waste
Savings in protection supplies
Real-time checkup in the office
Radiation safety control in high radiation areas
Ⅵ. OSART GOOD PRACTICE
□ IAEA OSART Review Duration : 2007. 4.16 ~ 5.3
Reviewed items
- 7 items besides management, organization, &
administration sections of YGN 5&6
Result of review in Radiation Protection Section
- 2 good practices out of 10 good practices
(No proposal for improvement) - CCTV System was evaluated as “Good Practice” the other is RIS (Radiation Information System)
Ⅵ. Conclusion
Radiation safety control is requisites for lasting nuclear industry
Our various efforts will help to improve radiation safety control whether it is large or not Actually, CCTV system is small effort but the such effort will makes a good fruit
Our will and endeavor should be followedOur will and endeavor should be followed
Maintenance of Leak Valve (SI-V522)
Maintenance of leak Valve (SI-V522)
□ KHNP(Korea Hydro & Nuclear Power) OrganizationHeadquarters
Branches
President & CEO
Nuclear Power SiteNuclear Power Site
Nuclear PowerEducation Inst.
Kori
Nuclear PowerEnviron. Tech. Inst.
Radiation HealthResearch Inst.
Hydro Power
QA Office
Plan & Admin Div.Plan & Admin Div. Project Div.Project Div.
PI Office
Han-gang Hydro Power
Radwaste Project Div.Radwaste Project Div.
Radwaste ProjectSite OfficeNew York Office
Paris Office
Yonggwang Wolsong Ulchin
Power Gen. Div.Power Gen. Div.
Gen. Admin. Office
Plant 1 (Unit1&2)
Plant 2 (Unit3&4)
Plant 3 (Unit5&6)
Comm. & Envir. Off.
KHNP Overview
Auditor Audit Office
Ulchin #1,2,3,4,5,6 (Shin-Ulchin #1,2)
◎ Seoul
Kori #1,2,3,4(Shin-Kori #1,2,3,4)
Wolsong #1,2,3,4 (Shin-Wolsong #1,2)
In OperationUnder
Const/PlanedTotal
4 (3,137)2 (2,000),
2 (2,800)/ - 8 (7,937)
4 (2,779)2 (2,000)/
-6 (4,779)
6 (5,900) - 6 (5,900)
6 (5,900) - /2(2,800)
8 (8,700)
20 (17,716) 8 (9,600) 24 (21,716)
Unit (MW)Site
Kori
Wolsong
Yonggwang
Ulchin
Total
□ Status of Nuclear Power Plants
Yonggwang#1,2,3,4,5,6
KHNP Overview [cont’d]
20 units (17,716 MW)
Project Unit ReactorType
Capacity(Mwe)
NSSSSupplier A/E COD
Yonggwang
#1#2#3#4#5#6
PWRPWRPWRPWRPWRPWR
9509501,0001,0001,0001,000
W/HW/HDOOSANDOOSANDOOSANDOOSAN
Bechtel/KOPECBechtel/KOPECKOPECKOPECKOPECKOPEC
Aug. 1986Jun. 1987Mar. 1995Jan. 1996May 2002Dec. 2002
Kori
#1#2#3#4
PWRPWRPWRPWR
587650950950
W/HW/HW/HW/H
GilbertGilbertBechtel/KOPECBechtel/KOPEC
Apr. 1978July 1983Sep. 1985Apr. 1986
Wolsong
#1#2#3#4
PHWRPHWRPHWRPHWR
679700700700
AECLAECLAECLAECL
AECLAECL/KOPECAECL/KOPECAECL/KOPEC
Apr. 1983Jun. 1997Jun. 1998Sep. 1999
Ulchin
#1#2#3#4 #5#6
PWRPWRPWRPWRPWRPWR
9509501,0001,0001,0001,000
FramatomeFramatome DOOSANDOOSANDOOSANDOOSAN
FramatomeFramatome KOPECKOPECKOPECKOPEC
Sep.1988Sep. 1989Aug. 1998Dec. 1999July 2004Apr. 2005
□ Nuclear Power Plants in Operation
KHNP Overview [cont’d]
Project Unit ReactorType
Capacity(Mwe)
PlantType COD Remark
Shin-Kori
#1 PWR 1,000 *OPR1000 Dec. 2010
Under Construction
#2 PWR 1,000 OPR1000 Dec. 2011
#3 PWR 1,400 *APR1400 Sep. 2013
#4 PWR 1,400 APR1400 Sep. 2014
Shin-Wolsong
#1 PWR 1,000 OPR1000 Oct. 2011Under
Construction#2 PWR 1,000 OPR1000 Oct. 2012
Shin-Ulchin
#1 PWR 1,400 APR1400 Dec. 2014Planned
#2 PWR 1,400 APR1400 Dec. 2015
8 units (9,600 MW)
* OPR : Optimized power Reactor* APR : Advanced power Reactor
□ NPP planned or under Construction
KHNP Overview [cont’d]
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