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ICHN PKOREA HYDRO & NUCLEAR POWER CO., LTD
70-1312-gil, Yuseong-daero, Yuseong-gu, Daejeon, 305-343, KOREATel: +82-42-870-5740 / Fax: +82-42-870-5779http://www.khnp.co.kr
July 9, 2014Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001
Attention: Mr. Jeffrey Ciocco Project No.0782Division of New Reactor Licensing MKD/NW- 14-0021L
Subject: Revised Responses to Initial Requests for Additional Information to Develop aMELCOR Input Deck for APR1400
Reference: 1) ERI Letter to NRC (ERI/NRC 2014-01-24B), dated January 24, 20142) KHNP Letter to NRC (MKD/NW-14-0014L): "KHNP Responses to InitialRequests for Additional Information to Develop a MELCOR Input Deck forAPR1400", dated June 2, 2014
KHNP is hereby submitting the revised responses to the initial Requests for AdditionalInformation (RAIs) to develop a MELCOR input deck for the APR1400. This response addressesall the questions of the RAI including 1.1-18, 1.1-30, 1.2-4, 1.3-17, and 1.3-19, which werescheduled to be provided by the end of June. Please note that each RAI is numbered for trackingpurpose.
Enclosure 1 contains one copy of the associated affidavit. Enclosure 2 provides KHNPResponses to Initial Requests for Additional Information to Develop a MELCOR Input Deck forAPR1400 (Proprietary). Drawings associated with Enclosure 2 are provided as electronic files ina CD or as a hardcopy, which are mailed to Document Control Desk.
If additional information or clarification is required, please contact Yunho Kim, Director ofKHINP Washington DC Center at [email protected] or 703-388-0592.
Sincerely,
Myung-Ki KimProject ManagerAdvanced Reactors Development LaboratoryKorea Hydro and Nuclear Power Co., Ltd
Enclosure:1. Affidavit KAW-14-00212. KHNP Responses to Initial Requests for Additional Information to Develop a MELCOR InputDeck for APR 1400 (Proprietary)
la
ICHNPKOREA HYDRO & NUCLEAR POWER CO., LTD
ENCLOSURE 1
Affidavit KAW-14-0021
I, Jae-yong Lee, state the following:
1. I am the Director of Korea Hydro & Nuclear Power Co., Ltd. (KHNP), and as such I amauthorized to request withholding the information transmitted with this letter from publicdisclosure and to execute this affidavit.
2. I am familiar with the criteria applied by KJ-INP to determine whether certaininformation is proprietary, and with the policies established by KHNP to ensure theproper application of these criteria.
3. The information, KI-INP Response to Initial Requests for Additional Information toDevelop a MELCOR Input Deck for APR1400 (Proprietary), transmitted with this letterhas been classified by KHNP as proprietary in accordance with the policies for thecontrol and protection of proprietary and confidential information. The informationregarded as proprietary is identified and marked consistent with the requirements of 10
CFR 2.390, § (b)(1)(i). Accordingly, the proprietary information is enclosed withinbrackets and the right-hand bracket carries a notation of "TS" to indicate that the tradesecret nature of the information claimed to be proprietary is the basis for proposing thatthe information so identified be withheld from public disclosure.
4. Pursuant to the considerations set forth in 10 CFR Section 2.3 90(a), KHNP considers theinformation classified as proprietary to be "trade secret" information since it is design,analysis, or test information that would be difficult for a competitor to reproduce andhence provides an economic and competitive advantage to KHNP.
5. The need for designating the information as proprietary has been raised within KHNP.The information is being treated proprietary and confidential and has not been disclosedby KHNP to the public.
6. Nondisclosure of the proprietary information transmitted with this letter is vital to thecompetitiveness held by KHNP and, hence, disclosure of the proprietary informationtransmitted in with this letter would have negative commercial impacts on thecompetitive position of KHNP in the U.S. nuclear market.
7. In accordance with KHNP policy, proprietary information contained in this documentmay be, or may have been, made available on a limited basis to regulatory bodies,customers, potential customers, and their agents, suppliers, and licensees, and othersunder suitable agreements providing for nondisclosure and limited use of the information.
4, IHNPKOREA HYDRO & NUCLEAR POWER CO., LTD
I declare that the foregoing statements are true and correct to the best of my knowledge,information and belief.
Executed on July 9, 2014.
e-yong LccDirectorAPR1400 Licensing TeamKorea Hydro & Nuclear Power Co., Ltd.
Associated Documents & Drawings
Hard Copy Only: Electronic files of the attached
documents & drawings are not provided
Jongtae SeoShin-Kori 3&4 Project MKEPCO Engineering & CCompany, Inc.150 Deolkin-Dong, YuseoDaejeon, Korea, 305-353
Transmittal No. : ANRH-14Date : '1Z 01. 10
KEPCO E&C'S TRANSMITTAL
To :
Mager NMr. Taeshik Kang
onstruction Shin-Kodi 3&4 Project ManagerDoosan Heavy Industries &
ng-Gu, Construction Co., Ltd.1338-12, Seocho 2-dong, Seocho-gu,Seoul, Korea, 137-860
Contract No. : DOOSAN/KPE-06-SKN3&4
The following listed documents are submitted to DOOSAN
in accordance with the Contract App. 2 and App. 6.
A ApprovalR: ReviewI Information
DS : Design Data StatusAS Approval Status
DOCUMENT NUMBER FOR__AR QT'Y
Project Doc/Dwg. No. DS E & DOCUMENT TITLE A
KEPCO E&C PG V TYPE AR S
Doc&Dw. No. , :__ _ _
9-1'13-Z-404-01C68 1 05 8P Design Specification for Reactor Vessel Insulation x
3L186-FS-DS91O
lul !Ul I U
KEPCO E&C(NSSS SD)'s Comments: KEPCO E&C(SD)
- Main text 56 pages, Appendices A 2 pages, B 10 pages
Name /Signatud
T ,-F-. IF T Date-I
U , I L Z M 4 9AF! ,|~ , I; ,il .•I H I,.I !r
~4A1AI4J~.
Latest Revision of References
for 3L186-FS-DS910, DDS-1, Rev.05
1. 3L186-FS-OS001, Rev.04
2. E-3L186-232-001, Rev.06
3. E-3L186-912-001, Rev.01
4. E-3L186-232-002, Rev.04
5. E-3L186-220-100, Rev.02
6. E-3L186-232-003, Rev.05
7. E-3L186-232-010, Rev.05
8. E-3L186-232-055, Rev.03
9-113-Z-404-001C
3LI86-FS-DS910
KEPCO E&C Shin-Kori Units 3 and 4 Revision 05
NSSS Division Design Data Status 1
Non Nuclear Safety Related
DESIGN SPECIFICATIONFOR
REACTOR VESSEL INSULATION
This document is the property of KEPCO Engineering & Construction Company, Inc. (KEPCO E&C) and is
to be used only for the purposes of the agreement with KEPCO E&C pursuant to which It is furnished.
The user of this document shall comply with all limitations or restrictions imposed upon any transfer
or disclosure of the information pursuant to the export control laws, regulations and rulings of the
Republic of Korea.
Issue Date z 01/09/2012
Prepared by Sung Ki Suh 5-41 Cognizant Engineer, PRIMARY FLUID SYSTEM ENGINEERING GROUP 1Z/22/2011
Reviewed by Gyu Sung Han 64'141- Reviewer, PRIMARY FLUID SYSTEM ENGINEERING GROUP 01/06/2012
Approved by Byung Jin Lee • Eng.Group Supervisor. PRIMARY FLUID SYSTEM ENGINEERING GROUP 01/06/2012
Approved by So Jin Baik e&l- Department Manager, NUCLEAR SYSTEM ENGINEERING DEPARTMENT 01/06/2012
Approved by Jong Tae Seo for[ Project Manager 01/09/2012
9-113-Z-404-O01C
Record of Revisions
Rev Date Sections/Pages Involved Reason for Revision DesignNo. I Status
00 03/29/2007 ALL Original Issue 2
201 11/29/2007 3.2.4, 6.2.1.3, 6.2.2.4,6.2.2.5, 6.2.3.2, Figure 2,
Figure 4-1, Figure 4-3, Figure
5. Figure 6, Figure 7, Figure 8,
6.2.1.7
02 06/30/2008 6.2.1.8, 6.2.3.2
1.3.1, 2.2, 3.1.1. 3.2.9,
3.2.14, 3.4.1, 3.4.6, 4.2.3.
5.1.3, 5.1.3.1, 5.1.4, 6.1.3.
6.1.15, 6.2.1.2, 6.2.1.8,
6.2.1.11, 6.2.2.5, 6.2.4.5. 7.1,
Figure 1, Figure 5, Figure 7
03 03/30/2010 2.2, 6.2.2, 6.2.3, 7.1.6, Figure
7, Figure 8
3.4.3. 3.4.9, 3.4.10, 4.1,4.2.2, 4.2.3, 5.1.5.2, 5.4.1,
5.6.1, 5.7.2, 6.1.4, 6.1.9,6.1.15, 6.1.18, 6.1.19, 6.2.1.5,
6.2.3.1, 6.2.3.2, 6.2.3.3,
6.2.3.4, 6.2.3.5, 6.2.3.6,
6.2.3.7, 6.2.3.8, 6.2.3.9,
6.2.3.10, 6.2.3.11, 6.2.3.12,
6.2.3.13, 6.2.3.14, 6.2.3.15,
6.2.3.16, 6.2.3.17, 6.2.3.18,
6.2.3.19, 6.2.3.20, 6.2.3.21,
6.2.3.22, 6.2.3.23, 6.2.3.24,
6.2.4.6. 7.1.6, Figure 3, Figure
4-3, Figure 7, Figure 9, Figure
10, Appendix B
04 03/30/2011 1.2, 2.1, 2.2
3.2.15, 3.2.16, 6.2.1.3, 6.2.4.7
DOOSAN comment resolution
Technical evaluation
DOOSAN Comments Resolution
Technical Evaluation
I1
Editorial Correction
Technical Evaluation
Editorial Correction
Technical Evaluation
1
1
3L186-FS-DS910 DDS-1i Rev. 05 Page 2 of 56
9-113-Z-404-001C
Record of Revisions
Rev. Date Sections/Pages Involved I Reason for Revision Design
No. I Status I
05 01/09/2012 2.2, 6.2.2.7. Table 1, Figure 3 Technical Evaluation 1
6.2.2.8, 6.2.2.9, Figure 1 Editorial
3L186-FS-DS910 DDS-1 Rev. 05 Page 3 of 56
9-113-Z-404-001C
TABLE OF CONTENTS
Section Title Pame No.
Record of Revisions 2
1.0 SCOPE 7
1.1 General 7
1.2 Contract Participants 7
1.3 Works Included 7
1.4 Interfaces Equipment and Services 8
2.0 ABBREVIATIONS AND DEFINITIONS 8
2.1 Design Data Status 8
2.2 Abbreviations 9
3.0 APPLICABLE REFERENCES 10
3.1 Purchaser's Specification 10
3.2 Purchaser's Drawings 10
3.3 Codes 11
3.4 Standards 11
3.5 Conflicts 12
4.0 QUALITY STANDARDS 12
4.1 Quality Class Classifications 12
4.2 Quality Assurance Requirements 12
5.0 SUBMITTALS 13
5.1 General Requirements 13
5.2 Drawings 16
5.3 Instruction Manuals and Technical Documents 18
5.4 Documents to Be Submitted with Proposal 19
5.5 Documents Required to Be Submitted for Approval Prior to 19
Material Release
5.6 Documents Required to Be Submitted for Approval Prior to 19
Fabrication Release
5.7 Documents Required to Be Submitted for Approval Prior to 20
Release for Shipment
3L186-FS-DS910 DDS-1 Rev. 05 Page 4 of 56
9-1 13-Z-404-001C
TABLE OF CONTENTS (Cont'd)
Section Title Page No.
5.8 Documents Required to Be Submitted for Approval/Information 20
Prior to Release for Shipment
5.9 Documents not Submitted but Available for Review in 20
Supplier's Shop
5.10 Documents to be Presented/Submitted to the Purchaser 21
by the Supplier at the Time of Final Inspection
6.0 DESIGN REQUIREMENTS 22
6.1 General Requirements 22
6.2 Detailed Design Requirements 25
6.2.1 Reactor Vessel Closure Head Insulation 25
6.2.2 Reactor Vessel Insulation including Lower Head Insulation for 28
Normal Operation
6.2.3 Reactor Vessel Insulation including Lower Head Insulation for 30
ERVC Operation
6.2.4 Reactor Vessel Insulation Requirements to Allow Insulation of 33
the ALMS and LPMS Sensors and their Covers
7.0 MATERIAL AND FABRICATION 34
7.1 Material Requirements 34
8.0 CLEANING 35
8.1 Cleaning Requirements 35
9.0 IDENTIFICATION 35
10.0 PACKAGING, SHIPPING AND SHIPPING CONTAINERS 35
10.1 Packaging Requirements 35
10.2 Shipping Requirements 35
10.3 Shipping Container Requirements 35
3L186-FS-DS910 DDS-1 Rev. 05 Page 5 of 56
9-113-Z-404-001C
LIST OF TABLES
Table No. Title Paee No.
1 SUPPLIER DOCUMENT SUBMITTAL SCHEDULE 36
2 LPMS SENSOR LOCATIONS ON THE REACTOR VESSEL 37
3 ALMS SENSOR LOCATIONS ON THE REACTOR VESSEL 38
LIST OF FIGURES
Fimire No. TitLe Page No.
1 CEDM NOZZLE THERMAL AND INSULATION DATA 39
2 RV SUPPORT INSULATION REQUIREMENTS 40
3 RV SHEAR KEY INSULATION REQUIREMENTS 43
4 REACTOR CAVITY STRUCTURE REQUIREMENTS 45
5 THERMAL AND INSULATION DATA OF THE 48
INTEGRATED HEAD ASSEMBLY AND DOME AREA
6 REACTOR CAVITY PERMANENT POOL SEAL 49
ASSEMBLY ENVELOPE
7 RV SHELL AND STEAM/WATER VENTING PORT 50
REQUIREMENTS8 ICI NOZZLE THERMAL, INSULATION AND PASSIVE 53
COOLING WATER INGRESSION PORT REQUIREMENTS
9 RV WALL TEMPERATURE REQUIREMENTS FOR 55
IVR-ERVC
10 REACTOR CAVITY GEOMETRY 56
LIST OF APPENDICES
Letter Title Page No.
A OUTLINE/INTERFACE DRAWING REQUIREMENTS A1-A2
B SEISMIC, BLPB AND IRWST DISCHARGE RESPONSE SPEMRA B1-Bl0
3L186-FS-DS910 DDS-1 Rev. 05 Page 6 of 56
9-113-Z-404-001C
1.0 SCOPE
1.1 General
1.1.1 This specification covers the design, fabrication, inspection, testing, quality
assurance, documentation, cleaning, packaging and shipping of Reactor Vessel
Insulation to be installed in Shin-Kori Nuclear Power Plant Units 3 and 4
(SKN 3&4).
1.1.2 The manufacturer of equipment supplied under this specification will be
referred to as the Supplier, and Doosan Heavy Industries and Construction
Co., Ltd. (DOOSAN) as the Purchaser.
1.1.3 The word "shall" is used to express an interface requirement that is
mandatory. The word "should" is used to express an interface
recommendation that is not mandatory.
1.2 Contract Particivants
The following identifies the SKN 3&4 contract participants referred to within
this specification.(1) System Designer (SD) - KEPCO E&C(N)
(2) Component Designer (CD) - DOOSAN
(3) Equipment Supplier (ES) - Manufacturer
(4) Plant Owner KHNP
1.3 Works Included
1.3.1 Works to Be Provided by the Equipment Supplier
The Supplier of this equipment shall be responsible for the design, material
procurement, fabrication, examination, testing, cleaning, painting, shipping of
the equipment described in this specification. Approval of the Supplier's
drawings, procedures, calculations, or tests by the Purchaser, does not relieve
the Supplier of these responsibilities.
1.32 The Supplier shall furnish insulation consisting of semi-permanent and
removable types for the reactor vessel and insulation support. The insulation
shall be fabricated in accordance with Reference 3.4.3 if reflective, or
Reference 3.4.5 if non-metallic, and shall comply with all requirements of this
specification.
3L186-FS-DS910 DDS-1 Rev. 05 Page 7 of 56
9-113-Z-404-OOC
1.3.3 Installation in the field in accordance with assembly instructions shall be
provided by the Purchaser. The Supplier shall include separately in his
proposal, cost data for providing the services of a field engineer to supervise
the insulation assembly.
1.4 Interfaces Eauinment and Services
1.4.1 Detail drawings of the reactor vessel surrounding structures and supports will
be furnished by the Purchaser as required to assist the Supplier in designing
the insulation.
1A.2 Embedment shown on Figure 4-3 will be furnished by others.
2.0 ABBREVIATIONS AND DEFIITIONS
2.1 Design Data Status
The status of each design requirement is indicated according to the following
designations when appropriate:
Design Data Status 1 (DDS-1)
Verified information provided for use in final design, analysis, and
documentation. Verified means documented in accordance with KEPCO E&C's
NSSS Quality Assurance Program (QAP).
Design Data Status 2 (DDS-2)
Information provided for material ordering and sizing purposes and for
preliminary calculations, based on assumptions requiring confirmation.
Design Data Status 3 (DDS-3)
Information provided for preliminary use, but not verified for this specific
application.
Each page has a Design Data Status (DDS) classification which is the lower
DDS for any information item on that page where DDS-3 is the lowest. The
entire document has a DDS classification which is the lowest classification of
any information contained within the document.
3L186-FS-DS910 DDS-1 Rev. 05 Page 8 of 56
9-113-Z-404-001C
2.2 Abbreviations
ALMSANSIASMEASTMBAMPB/MBLPBCEACEDMCD-ROMCETCPSDOOSANDVIERVCHvrHJTCICIID
MIAIMQPIRWSTKEPCOKEPCO E&C(N)
KHNPLPMSLOCAMCRNSSSNIMSODPNSRCSRCGVSRFQRPVRVHRVISCUMSCPSSETSCUSNRC
Acoustic Leak Monitoring SystemAmerican National Standards Institute
American Society of Mechanical Engineers
American Society for Testing and Materials
Boric Acid Makeup PumpBill of MaterialBranch Line Pipe BreakControl Element Assemblies
Control Element Drive MechanismCompact Disk - Read Only Memories
Core Exit ThermocoupleCycles Per SecondDOOSAN Heavy Industries & Construction Co., Ltd.
Direct Vessel InjectionExternal Reactor Vessel Cooling
Hot Functional TestHeated Junction Thermo CoupleIn-Core InstrumentInner DiameterIntegrated Head AssemblyIntegrated Manufacturing and Quality Plan
In-containment Refueling Water Storage Tank
Korea Electric Power CorporationKEPCO Engineering & Construction Company, Inc.,
NSSS DivisionKorea Hydro & Nuclear Power Co., Ltd.
Loose Parts Monitoring System
Loss Of Coolant AccidentMain Control RoomNuclear Steam Supply System
NSSS Integrity Monitoring SystemOuter DiameterProject Numbering SystemReactor Cooling SystemReactor Coolant Gas Vent System
Request For QuotationReactor Pressure VesselReactor Vessel HeadReactor Vessel InsulationStandard Cubic Foot per Minute
Shutdown Cooling PumpSafe Shutdown EarthquakeTechnical Support Center
United State Nuclear Regulatory Commission
I
3L186-FS-DS910 DDS-1 Rev. 05 Page 9 of 56
9-113-Z-404-001C
3.0 APPLICABLE REFERENCES
The following references shall be used as required in the text of this
specification for construction of this component. The latest addenda, revisions,
and editions except Purchaser's Specification, in effect as of December 31, 2001
shall apply unless a specific date is referenced below. For the Purchaser's
Specification and Drawing, the latest revisions shall be used unless otherwise
specified. The latest revision of the Purchaser's Specification shall be controlled
and distributed to the Supplier by the Purchaser.
3.1 Purchaser's Specification
3.1.1 Design Specification for Cleaning and Painting Requirements for Nuclear
Components, 3L186-FS-DS001.
3.2 Purchaser's Drawinrs (Latest revisions aunlied)
The Purchaser will provide the latest revisions of the following Drawing.
3.2.1 E-3L186-232-001, Integrated Head Assembly Arrangement and Interfaces
3.2.2 D-HC-11162-C03, Reactor Vessel External Interfaces
3.2.3 E-3L186-912-001, Reactor Cavity Pool Seal Outline Arrangement
3.2.4 D-HC-12100-CO1(2SH), D-HD-12100-CO1(2SH), D-HC-12100-C02(2SH), and
D-HD-12100-C02(2SH), Reactor Internals Dimensional Assembly
3.2.5 E-3L186-232-002, Reactor Vessel Closure Head Requirements
3.2.6 D-HC-11125-COI, Reactor Vessel Inlet Nozzle
32.7 D-HC-11126-CO1, Reactor Vessel Outlet Nozzle
3.2.8 D-HC-11142-CO1, Reactor Vessel Bottom Head Nozzles
3.2.9 12665-49004, NIMS Mechanical Mounting and Interface Outline
3.2.10 E-3L186-220--100, Reactor Vessel Arrangement and Installation
3L186-FS-DS910 DDS-1 Rev. 05 Page 10 of 56
9-113-Z-404-OO1C
3.2.11
3.2.12
3.2.13
3.2.14
3.2.15
3.2.16
E-3LI86-232-003 Vent Pipe & Valve Arrangement
E-3L186-232-010 Integrated Head Assembly Cooling Shroud Assembly
D-HC-11127-CO1 Direct Vessel Injection Nozzle
E-3L186-232-055 ALMS/LPMS Cable Routing
D-HC-24141-COI, D-HC-24141-C02, D-HC-24141-C03 and D-HC-24141-C04
Cold Leg Piping
D-HC-24171-CO1 and D-HC-24171-C02 Hot Leg Piping
3.3 Codes
3.3.1 ASME Boiler and Pressure Vessel Code, Section XI, excluding App. VIII,
Rules for Inservice Inspection of Nuclear Power Plant Components, 1995
Edition with 1995, 1996, and 1997 Addenda.
3.4 Standards
3.4.1 ASTM C 168-2000, Standard Terminology Relating to Thermal Insulation.
3.4.2 ASTM C 1061-1986, Standard Test Methods for Thermal Transmission
Properties of Non-homogeneous Insulation Panels Installed Vertically.
3.4.3 ASTM C 667-2001, Standard Specification for Prefabricated Reflective
Insulation Systems for Fquipment and Pipe Operating at Temperatures Above
Ambient Air.
3.4.4 ASME NQA-1(Part II and IIf)-1994 edition with 1995 Addenda, Quality
Assurance Requirements for Nuclear Facility Applications.
3.4.5 NRC Regulatory Guide 1.36, Rev.0, February 1973, Nonmetallic Thermal
Insulation for Austenitic Stainless Steel.
3.4.6 ASME Y14.1-1995, Decimal Inch Drawing Sheet Size and Format
3.4.7 USNRC Regulatory Guide 1.82, Rev.02, May 1996, Water Sources for
3L186-FS-DS910 DDS-1 Rev. 05 Page. 11 of 56
9-113-Z-404-OO1C
Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident.
3.4.8 ASTM C 680-1989(R1995), Practice for Determination of Heat Gain & Loss
and the Surface Temperature of Insulated Pipe & Equipment Systems by the
use of a Computer Program.
3.4.9 ASTM C 1363-1997, Standard Test Method for the Thermal Performance of
Building Assemblies by Means of a Hot Box Apparatus.
3A-10 = Std 344-1987 (Reaffirmed 1993) as modified by USNRC Regulatory Guide
1.100, Revision 2, dated June 1988, IEER Recommended Practice for Seismic
Qualification of Class 1E Equipment for Nuclear Power Generating Stations.
3.5 Conflicts
The Supplier shall be responsible for assuring that all the requirements of
this specification are complied with unless exceptions are stated in writing
with the Supplier's proposal. No deviation will be permitted without approval
by the Purchaser. Any conflict with or within this specification or its
references shall be brought to the attention of the Purchaser for resolution
prior to any action by the Supplier.
4.0 QUALITY STANDARDS
4.1 Quality Class Classifications
The Reactor Vessel insulation is classified as Quality Class 2(T).
4.2 Quality Assurance Reouirements
4.2.1 The Purchaser, his customer, and his customer's representative shall have
access to the Supplier's shop during fabrication and testing.
4.2.2 The Supplier's Quality Assurance Program shall conform to the requirements
of Purchaser's Supplier Quality Assurance Program Specification for Quality
Class 2(T) and shall be reviewed by Purchaser.
4.2.3 The Supplier's Integrated Manufacturing and Quality Plan's(IMQP)
3L186-FS-DS910 DDS-1 Rev. 05 Page 12 of 56
9-113-Z-404-001C
procedures, and quality records shall be in accordance with the requirements
of Purchaser's Supplier Quality Assurance Program Specification for Quality
Class 2(T), and Section 5.0 and Appendix A of this specification.
4.2.4 The material supplier shall certify that all insulation materials provided meet
the requirements of this specification.
4.2.5 The insulation furnished shall be constructed in a professional manner, care
being taken to meet all dimensional requirements on the approved
construction drawings.
4.2.6 The Supplier shall notify the Purchaser ten(10) working days prior to
conducting the tests required by Paragraph 6.1.3. The test shall not be
performed until the Purchaser, the Purchaser's representative and Customer's
representative of Purchaser are present or this hold point has been waived.
4.2.7 The Supplier shall notify the Purchaser ten(10) working days prior to
shipment for a release inspection.
5.0 SUBMITTALS
5.1 General Reguirements
5.1.1 Documents shall be submitted as specified below.
5.1.1.1 Documents shall be in the English language. But the scales and ranges of
instrumentation shall be in the SI(metric) system. A reproduction must be of
high quality having sharp black, clean, well defined lines with a line density
equal to or better than the original.
5.1.1.2 The engineering process may be carried out in the English unit system and
the resulting documents may be in English units, except the Instruction
Manual which shall be in metric units. However, for procurement in Korea,
the metric system will be used unless the use of English units is more
practical and approved by the Customer. Dual units may be permiLted if
necessary.
5.1.1.3 Supplier documents shall include both the Supplier's and Purchaser's
3L186-FS-DS910 DDS-1 Rev. 05 Page 13 of 56
9-113-Z-404-001C
document number. Purchaser will provide the Purchaser's document number
to the Supplier.
5.1.1.4 Drawings and Documents shall be accompanied by a letter of transmittal
marked to show Owner's order number and contract number.
5.1.1.5 Documents are required to be submitted on or before the schedule given
below.
5.1.1.5.1 Documents identified to be submitted to the Purchaser prior to the Material
Release, Fabrication Release, or Release for Shipment events, shall be
submitted at least 12 weeks prior to that event.
5.1.1.5.2 A specific list of documents and firm dates for submittal shall be negotiated
prior to placement of the Purchase Order. This schedule shall support the
required material, fabrication, and release for shipment dates. The specific
documents required and their required submittal dates shall be listed on a
form similar to Table 1 of this Specification and will be made an Attachment
to the Purchase Order.
5.1.2 Submittal required by this Specification will fall into one of the following
categories.
5.1.2.1 Submitted for Approval - Purchaser's approval must be obtained before
proceeding with the activity associated with the document.
5.1-2.2 Submitted for Information - No comment will be provided by the Purchaser
unless a direct specification violation is observed. The Supplier should
proceed with the activity associated with the document without delay.
5.1.2.3 Documents available for review in the Supplier's shop - These are
documents that will be available for review and information in the Supplier's
shop. These documents shall be available for submittal to the Purchaser upon
request
5.1.3 Documents submitted for approval to the Purchaser will be assigned an
approval category after they are processed by the Purchaser. Definitions of
the approval categories are as follows:
3L186-FS-DS910 DDS-1 Rev. 05 Page 14 of 56
9-113-Z-404-001C
ApprovalCategory Definitions
I Work may proceed.
2 Revise and resubmit. Work may proceed subject to
incorporation of change indicated.
3 Revise and resubmit. Work may not proceed until change is
approved.4 For information, client & A/E distribution only.
5 For information, A/E distribution only.
6 Void or superseded.
U Unacceptable for reproduction. Resubmit.
5.1.3.1 The Supplier shall incorporate changes as required by comments on the
drawings or documents and resubmit correct drawings or documents for
permission to proceed within 3 weeks.
Drawings or documents having received previous permission to proceed will
not be changed without prior notification of the Purchaser. Changes to such
drawings or data by the Supplier shall be clearly identified and shall be
resubmitted to the Purchaser for Purchaser's permission to proceed.
5.1.4 The standard quantities for document submittal shall be as follows.
5.1.4.1 Eight(8) copies of written documents suitable for reproduction for approval
5.1.4.2 Four(4) prints and four(4) reproducibles and two(2) CD-ROMs of drawings
for approval.
5.1.4.3 Ten(10) copies of written documents suitable for reproduction for final
transmittal.
5.1.4.4 Seven(7) prints and six(6) reproducibles and five(5) CD-ROMs of drawings
for final submittal.
5.1.4.5 Five(5) copies of the preliminary technical manuals and thirty-three(33) copies
and one(l) CD-ROM of the approved technical manuals.
5.1.4.6 Nineteen(19) copies and one(l) CD-ROM of spare part list and consumables
list.
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5.1.4.7 Five(5) copies and one(l) CD-ROM of quality records documentation package.
5.1.5 Identification
5.1.5.1 All calculation, technical manuals, reports and procedures shall be identified
with at least the following pertinent information:
a) Supplier's Name
b) Document Title
c) Supplier's Document No., Revision and Date of Issue
d) Purchase Order Number
e) Purchaser's Name
f) SKN 3&4 Contract Number
g) Purchaser's Equipment Identification Number
h) Owner's Document Number
i) Owner's Item Number (PNS Number)*
* PNS Number will be provided separately by the Purchaser.
5.1.5.2 All detailed drawings shall be identified by the following title in the drawing
title block and shall be identified with at least the pertinent information
required by Paragraph 1.1 of Appendix A.
a) Shin-Kori Nuclear Power Plant Units 3&4
b) RVI (Assembly or Detail) including Passive Cooling Water Ingression
Assembly and Steam/Water Venting Assembly Drawings
c) Drawing Number (Purchaser's and Supplier's) and Revision Number
d) Owner's Item Number: (will be provided later by the Purchaser)
e) Owner's Drawing Number: (will be provided later by the Purchaser)
5.1.5.3 Drawings and Documents shall be accompanied by a letter of transmittal
marked to show Owner's order number and contract number.
5.1.5.4 Drawings and Documents shall be transmitted with stamp: either "For
Information", "For Approval", "For Construction", or "For Retention".
5.2 Drawings
5.2.1 All submitted drawings shall be of sufficiently high quality to permit
adequate reproduction.
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5.2.2 Drawings shall be in English units with the metric equivalents in
parentheses.
5.2.3 All drawings shall conform to the recommendations of Reference 3.4.6.
Minimum standards are considered to be as follows:
a) Lettering
All lettering shall appear upper case only, open style.
General lettering, minimum 5/32" (4 mm)
Title lettering, minimum 1/4" (6 mm)
Fractions, minimum 1/4" (6 mmm)
Space between characters and lines will allow sufficient readability on
printed material.
b) Line Work:
1) All lines shall be sharp, solid and sufficient density.
Line work width will not necessarily differ between object,
background and other notational types. All line widths shall insure
sufficient clarity for readability. Space between lines shall allow for
sufficient readability on printed reproducibles.
2) The quality of the Supplier generated drawings or submitted
reproductions of these drawings shall be such that every line and
character has sufficient clarity.
5.2.4 The Supplier shall make all corrections required by the Purchaser and
resubmit the drawing for approval. Each drawing change shall be briefly
described and each drawing revision shall be assigned a revision number.
5.2.5 The content of the Outline/Interface Drawings shall be in accordance with
the applicable requirements of Appendix A to this specification.
5.2.6 Drawings shall comply with the size requirements of Reference 3.4.6.
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L Drawings
a) General Arrangement drawings, P&ID, Outline drawing: D, E size7
b) Drawings, manufacturing and installation drawing: C, B or A size*
c) ISO drawings: C size*
2. Other technical documents: A or B size*
* Corresponding size (AW, Al, A2, A3, A4, and A5) may be used.
5.2.7 Drawing reproducibles shall be forwarded in mailing tubes. Folded drawing
reproducibles are not acceptable. Reproducibles (B size or larger) submitted
shall be Mylar-4 mil double mat polyester base film. Paper separators shall
be provided between each radiograph if two or more radiographs are packed
in one envelope.
5.2.8 CD-ROM shall be prepared for storing the information drawing, final
approved drawings and documents.
5.2.9 After receipt of the approved letter from the Purchaser, the Supplier shall
provide the drawings and documents on CD-ROM. The CD-ROM shall be
indexed to define the drawings and documents contained on the CD-ROM.
5.2.10 The electronic file format for drawing shall be vectorized CAD files, except
in case where the drawings is not drawn by the CAD system. In such cases,
only the scanned image files are provided.
5.3 Instruction Manuals and Technical Documents
5.3.1 The instruction manual shall include but is not limited to the information
required by Purchaser's Criteria for technical instruction manuals for
equipment supplied for installation in Nuclear Power Plants.
5.3.2 The instruction manual shall include the following:
a) Panel storage requirements at the site
b) Maximum gaps allowed between the panels
c) Maximum allowed panel offsets
d) Adequate instructions for field personnel to install the insulation (Note:
this requirement shall specify the method(s) to be used by field
personnel in maintaining proper panel elevations during installation.)
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e) Instruction to field personnel in fitting the insulation around supports,
pipe, etc. so as to keep air infiltration to a value assumed in the
insulation design
f) Instruction to field personnel who install the insulation on methods to be
used to close any and all field cuts made in the insulation to minimize
air infiltration.
5.3.3 Instruction manuals shall use the metric system.
5.3.4 Technical documents, including instruction manual, shall be A or B size of
Reference 3.4.6.
5.4 Documents to Be Submitted with Proposal
5.4.1 A complete description of proposed equipment that shall include at least the
following information:
a) Outline Drawing & Assembly of proposed equipment (insulation, passive
cooling water ingression assembly and steam/water venting assembly
etc.) including overall dimensions, required pull space, and support
configuration.
b) Proposed Bill of Materials
c) Estimated wet and dry weights
d) Accessories as specified
e) List and justification for all exceptions taken to this Specification
f) Date that material and fabrication must be released to meet required "On
Site" dateg) Date that the required documents will be submitted
h) Any "type test" information required by Request for Quotation (RFQ)
i) Notice of intent to test in lieu of seismic calculations, if applicable
j) Description of proposed method of meeting operability requirements, if
applicable.k) List of nuclear installations using the proposed equipment.
1) NRC Regulatory Guide 1.82 data per Paragraph 6.1.16.
5.5 Documents Reauired to Be Submitted for Approval Prior to Material Release
5.5.1 Insulation Assembly and Outline Drawing with Bill of Material.
5.6 Documents Recuired to Be Submitted for Approval Prior to Fabrication
Release
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5.6.1 Final Analytical Report demonstrating compliance with Paragraphs 6.2.1.2,
6.2.2.1 and 6.2.3.8, and the Seismic Report incorporating all analysis of this
Specification.
5.6.2 Thermal transfer test procedure required by Paragraph 6.1.3 of this
Specification.
5.7 Documents Reguired to Be Submitted for Approval Prior to Release for
Shi•ment
5.7.1 Five(5) copies of the preliminary technical manuals.
5.7.2 Thermal Transfer Test Report demonstrating compliance with Paragraphs 6.2.12
and 6.2.2.1.
5.8 Documents Required to Be Submitted for Approval/Information Prior to
Release for Shipment*
5.8.1 Quality Records Documentation Package per Purchaser Quality Assurance
Program".
5.8.2 Storage and Handling Procedures
5.8.3 Packaging Procedure
5.8.4 Shipping Procedure
5.8.5 Recommended Spare Parts List with Prices and Consumable List
5.8.6 Special Installation and Maintenance Tool List
5.8.7 Final Technical Manuals
5.8.8 Equipment Packing List
5.9 Documents not Submitted but Available for Review in Suonlier's Shop
5.9.1 Personnel Qualifications
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5.9.2 Miscellaneous Fabrication Procedures
5.9.3 NDE Procedures
5.10 Documents to Be Presented/Submitted to the Purchaser by the Sunplier at
the Time of Final Inspection
5.10.1 Outline/Interface Drawings with As-Built dimensions.
* Documents of subsections 5.8.2, 5.8.3, 5.8.4 and 5.8.7 should be submitted for
approval, the others for information.
** One CD-ROM of quality records documentation package may be submitted 2
week after shipment.
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6.0 DESIGN REQUIREMENTS
6.1 General Reuuirements
61.1 Weld seams of the reactor vessel and closure head will be periodically
inspected in accordance with Reference 3.3.1. The reactor vessel seams and
weldments will be inspected from inside the vessel and therefore there will
be no requirement for easy removal of the insulation. However, easy removal
of the Closure Head insulation shall be required for outside inspection.
6.1.2 The thermal transference (including conduction, convection and radiation heat
transfer), as defined by Reference 3.4.1, of not more than 0.14 Btu/hr-'F-f&
of insulated component surface area in conjunction with the environmental
conditions of Paragraphs 6.2.12 and 6.2.2.1 shall be used as the design basis
for all insulation.
The insulation shall satisfy the performance requirements in Paragraphs
6.2.1-2 and 6.2.2.1 with defined (by Supplier) allowances for such heat losses
which may occur as a result of un-insulated restraints, un-insulated piping
and component supports, piping and component supports which penetrate the
insulation, air infiltration, mechanical attachments, etc. to the insulated
components.
6.1.3 The thermal transference of the insulation shall be verified by tests according
to References 3.4.2 and/or 3.4.9. Testing to determine thermal transference
shall encompass representative segments of each insulation configuration (e.g.,
4 inch-thick panels with five layers per inch, 4 inch-thick panels with four
layers per inch, 3-1/2 inch-thick, etc.). The test sections shall replicate
installed sections and shall have a joint per Paragraph 6.1.7. The joint
orientation used in testing shall be consistent with installation requirements
(i.e., the joint in the test panel shall have the maximum gap allowed between
panels as stated in the installation instructions) and shall be described in the
test report. The effect of air velocity shown on Paragraphs 6.2.1.2 and 6.22-1
shall be considered by Langmuir's equation as described in Reference 3.4.8.
6.1.4 The insulation shall have a minimum design life of 60 years. The Supplier
technicalInstallation manual shall provide the maintenance and in-service
inspection or testing schedules and procedures required to maintain the design life
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of 60 years.
6.1.5 Reflective insulation shall form a system comprised of prefabricated units,
engineered as integrated assemblies to fit the surfaces to be insulated with
due allowances for thermal expansion, contraction and equipment deflection.
6.1.6 The insulation design shall provide a good fit to minimize air leakage losses
both inward and outward. The insulation shall be designed to prevent internal
air circulation and chimney effects and have adequate convection stops.
Panels and segments of units shall have overlapped edges.
6.1.7 The exterior sheathing need not be watertight but it shall enclose the
insulation and protect the insulation from a stream of water. The sheathing
shall retain the insulation in position and prevent compaction and/or
separation from the insulated component. All joints shall have a minimum 1
inch lap. A purchaser approved deformed joint may be used in lieu of lap for
circumferential joints between insulation units.
6.1.8 The thermal characteristics of the insulation shall not be adversely affected
by moisture, and the insulation shall have low water retention after wetting.
6.1.9 The insulation shall be self-draining and shall be capable of withstanding
without damage or loss of design insulation capabilities, two accidental
flooding with solution per Paragraph 7.1.5 during the design life.
6.1.10 Removable insulation, when specified, shall be easily removed and replaced
for inspection with no damage to the insulation, or equipment. Removable
sections shall be provided with handles and shall be small enough to be
handled by two men. The weight of a single segment shall not exceed 80
pounds. Insulation adjacent to removable units shall be independently
supported and unaffected by such removal. Buckle type fasteners used for
removable insulation shall be provided with a purchaser approved provision to
prevent inadvertent opening of the quick released fastener and subsequent
movement of the insulation panels.
6.1.11 The Supplier's method of insulation support is subject to Purchaser approval.
The insulation design shall not require any part to be welded to the reactor
coolant system pressure boundary. Reference drawings are provided so that
Supplier can provide the design concept of insulation support with his
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proposal, see Paragraph 3.2.
6.1.12 The insulation for horizontal surfaces shall be capable of supporting a 250
pound man without permanent deflection or distortion of the panel and shall
meet the upset conditions of Paragraph 6.2.1.2.
6.1.13 The insulation shall be designed to permit placing ladders against it without
affecting its insulating surface or support characteristics.
6.1.14 The insulation shall be designed to withstand a containment pressure test of
up to 69 psig and a subsequent external pressure (i.e., pressurization or
depressurization) rate of up to 15 psi/min and upset conditions in air
velocities. Insulation shall remain intact and incur no permanent damage as
the result of such tests.
6.1.15 The reactor vessel insulation design shall be such that during a SSE seismic,
BLPB event and IRWST discharge event, no piece, part, subassembly or
appurtenance can structurally fail and become a missile. This requirement
shall be documented in an analytical report that demonstrates that during the
seismic, BLPB event and IRWST discharge event, no insulation panel,
subassembly, fastener support or other insulation component is stressed above
the allowable yield strength for the material in question. The seismic, BLPB
and IRWST discharge response spectra to be utilized in this design analysis
are contained in the Appendix B. The stresses for any given direction
resulting from each seismic, BLPB and IRWST load shall be combined as the
square root of the sum of the squares or by some conservative method.
6.1.16 Insulation shall be suitable for use inside the containment and shall not
affected the performance and operation of containment sumps or spray
system. Reference 3.4.7 requires the owner to do a long-term recirculation
cooling analysis following a LOCA. The insulation provided by this
specification has to be considered in this analysis. Certain attributes of the
insulation such as sink rate, volume and type of potential debris, transport
data and pressure drop as a result of screen blockage can either come from
the Supplier or NRC data can be used. The Supplier in his proposal shall
state what information he will provide.
6.1.17 The surface temperature of the insulation except for dome area shall not
exceed 140'F for personnel access.
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6.1.18 The insulation is non-safety related component and seismic category II. The
insulation shall not impair the ability of seismic category I systems from
performing their safety functions during and following seismic design events.
6.1.19 Calculations or testing shall verify that the insulation design meets the seismiAc
design requirements of this specification and Reference 3.4-10.
6.2 Detailed Desiizn Reuuirements
6.2.1 Reactor Vessel Closure Head Insulation
6.2.1.1 The insulation for the reactor vessel closure head consists of two assemblies,
the flange insulation and the dome insulation. Reference 3.2.1 shows the
flange insulation in cross section and some of the dimensional constraints on
both of the assemblies. Figure 5 shows the MIA and dome insulation
configuration.
6.2.1.2 Insulation, as provided by the Supplier, shall limit heat loss from the reactor
vessel closure head to 31,000 Btu/hr when operating with the CEDM cooling
air conditions of Figures 1 and 5 and with following environmental
conditions:
(The 31,000 Btu/hr does not include the CEDM heat loss or the support
losses inside insulation, but does include reactor vessel flange losses, flange
support losses and leakage around the CEDM penetrations.)
Closure Head Surface Temperature 615°F
Relative Humidity of Ambient Air 100 %
Average Ambient Air Temnerature
Flange Area 120'F
Dome Area (Normal Condition) 95"F
Dome Area (Upset Condition*) 83'F
Average Velocity of Air Flowing Across Insulation
Flange Area 150 ft/min.
Dome Area (Normal Condition) 30 ft/sec.
Dome Area (Upset Condition*) 45 ft/sec.
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-9-113-Z-404-001C
Upset condition is defined as an overcooling event initiated when all
CEDM cooling fans are operating and shall be considered in evaluating
the mechanical integrity of the insulation without permanent deflection
or distortion of the insulation panel. The upset event are assumed to
occur not more than twelve(12) times per year.
6.2.1.3 The cylindrical portion of the flange insulation shall accommodate the vessel
flange OD as shown in Reference 3.2.2 and the permanent pool seal assembly
ID as shown in Reference 32.3. Figure 6 provides the reactor cavity
permanent pool seal assembly envelope. The horizontal disc, top portion of
this flange insulation, shall have an ID of 172 inches nominal(refer to
Reference 3.2.1). The top elevation of this disc shall not exceed 71.44 inches
above the mating surface and the lower elevation shall not be lower than
67.09 inches. This will accommodate the reactor vessel stud protrusion below
it. The flange insulation panels shall be designed to facilitate installation and
removal of the vertical and horizontal panel(s) as an assembled unit. Removal
is required for refueling and inservice inspection.
6.2.1.4 The dome insulation in elevation shall not exceed 99.4 inches above the
mating surface (refer to References 3.2.2 and 3.2.4). The OD of the dome
insulation shall be approximately equal to the ID of the IHA Cooling Shroud
Plate and shall provide a positive seal between the periphery of the insulation
panels and the internal periphery of the IHA Cooling Shroud Plate. The shape
of the dome insulation shall be to minimize the pressure drop at the
CEDM/HJTC cooling air pass. The minimum pressure drop can be achieved
by having the same curvature as reactor vessel closure head. The flat panel
should be applicable with maintaining cooling air flow area as much as
possible. Also, the dome insulation shall be designed not to block the air flow
below CEDM plenum plate of IHA. The IRA design is shown on Reference
3.2.1. The insulation design shall be evaluated by System Designer before the
final fabrication.
6.21.5 The dome insulation shall accommodate 103 CEDMV/HJTC nozzles and a vent
line with a pattern as shown on Reference 3.2.5. The dome insulation shall
accommodate the lift lugs/clevis, support columns, bottom ring plate and its
connection bolts etc. (refer to References 3.2.1, 3.2.5 and 3.2.12). The quick
removal and reusable type insulation shall be designed for the dome
insulation. It shall be possible to remove and reinstall the dome insulation
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without removal of IHA and damage to CEDM/HJTC nozzles. The minimum
diameter for the CEDM/HJTC openings shall be slightly larger than the
CEDM/HJTC nozzles and therefore nozzle insulation plugs are required.
These plugs shall seal any gap between the dome insulation panels and the
CEDM/HJTC nozzles. Theses plugs should be non-metallic insulation with
split thermal wrap cloth gasket- However, the thermal wrap cloth gasket shall
prevent insulation from resting directly on the nozzle or closure head surface.
These plugs may also be fixed semi-permanently to the nozzles (see Figure
1). These plugs shall not extend above a plane 3/4 inch below each
CEDM/HJTC nozzle "omega" seal weld (refer to Reference 3.2.5).
6.2.1.6 Figure 5 provides the requirements and data for closure head insulation
design and for heat transfer analyses information.
5.2.1.7 The inspection of the reactor vessel closure head and penetration nozzles will
be periodically performed. Sufficient space shall be provided to permit
inspection using special equipment. The dome insulation of reactor vessel
closure head shall be designed to maintain at least 2.5 inches above the
reactor vessel closure head surface (see Figure 5). At least 4 insulation
access openings of 16 x 16 inch for the inspection shall be provided at
appropriate locations where the CEDM/HJTC nozzles and IHA structure shall
not interfere with the access for the inspection work. The insulation shall be
designed, fabricated, and installed to allow the visual inspection of whole
closure head surface and CEDM/HJTC nozzles including the most outside
nozzles by the remote visual inspection devices (crawler, cable, etc.) without
removal of the insulation panel. The operating dimensions of visual inspection
devices for inspection shall be provided by the Purchaser.
6.2.1.8 The IHA access opening dimensions as shown in Reference 3.2.12 shall be
considered in the insulation access openings design for visual inspection as
required by the Purchaser (The insulation access opening design shall be
reviewed by the Purchaser.). The removable insulation access openings shall
be built into the insulation to coincide with access openings in the cooling
shroud shell. The purpose of these openings is to allow visual or remote
visual inspection of the CEDM/HJTC nozzles connections to the reactor
vessel top dome that are contained within the insulation enclosure. The
access opening shall not interfere with the RVH nozzles, IHA structure and
installed ALMS/LPMS sensor covers of the top dome inside area (refer to
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Reference 3.2.9 and Table 2, Table 3).
6.2.1.9 Insulation support should be equipped if it is necessary to support the dome
insulation.
6.2.1.10 Reactor Coolant Gas Vent System(RCGVS) nozzle location shall be considered
in dome insulation design (refer to References 3.2.2 and 3.2.11)-
6.2.1.11 Detail design of the structural angles for the flange insulation support with
the IHA cooling shroud shell and RV flange will be designed and furnished
by Component Designer. The structural angles shall be designed not to
interfere with the operation of the silgle stud tensioners (SST).
6.2.2 Reactor Vessel Insulation Including Lower Head Insulation for Normal
Operation
6.2.2.1 Insulation as provided by the Supplier shall limit the heat loss from the
reactor vessel and lower head (including inlet, outlet, DVI and ICI nozzles) to
163,000 Btu/hr when operating with the following environmental conditions:
Reactor Vessel Surface Temperature:
Around the outlet nozzle 615'F
Around the inlet nozzle and 5557F
remaining vessel surface
Relative humidity of ambient air 100 %
Average ambient air temperature:
Reactor Vessel Cavity refer to Figure 4-1
Average Velocity of Air Flowing Across Insulation:
Exterior Surface refer to Figure 4-1
Lower Head and Lower/Upper Streaming Shields refer to Figure 4-1
6.2.2.2 It is intended to install the reactor vessel and then install the reactor vessel
insulation. Whereas the lower shield plug will be in place at this time, the
upper shield plug will be installed after the insulation installation. The
Purchaser shall provide reactor cavity layout details to the Supplier as part of
his request for quotation (see Figure 4-2 and Reference 3.2.10).
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6.2.2.3 Removable insulation shall be provided around the reactor vessel inlet, outlet
and DVI nozzles. The reactor vessel support pads (on inlet nozzles) shall
not be insulated.
6.2.2.4 Insulation of the reactor vessel inlet and outlet nozzles shall extend radially
along the nozzle center lines a distance of 140.5 inch and 131.5 inch,
respectively. Piping insulation (by others) will abut this square-ended
insulation with an overlapped edge (refer to References 3.2.6, 3.2.7 and Figure
2). See Figure 2 for considerations around nozzles and vessel supports.
6.2.2.5 Insulation of the DVI vozzles shall extend radially along the nozzle center
lines a distance of 123.25 inch. Piping insulation (by others) will abut this
square-ended insulation with an overlapped edge (refer to Reference 3.2.13).
6.2.2.6 Insulation around the vessel shear key should be compressible and must be
flexible enough to allow relative thermal movement of the key with respect
to the fixed metallic removable insulation on the vessel (see Figure 3).
Minimum 0.5 inch clearance (air gap) is required between the periphery of
the insulation and the support base plate. This insulation may be
non-metallic. The difference between thermal conductivities of this insulation
along the fiber and perpendicular to the floor (the degree of anisotropism)
shall be small to prevent "cool spots" on the vessel wall. Crushable insulation
shall be provided between the keyway and the baseplate and the insulation
may be non-metallic.
6.2.2.7 In the RV shear key area, adequate space to withdraw and install the lower
expansion plate assemblies shall be provided to adjust a gap to meet the
rcquirement during the hot functional test (HFT). The RV insulation and its
suppori shall not also interfere with the access path to the lower expansion
plate assemblies. The interface dimension between RV baseplate and
insulation is shown in figure 3.
6.2.2.8 The in-core instrumentation consists of 61 instrument nozzles as shown in
Reference 3.2.8. The insulation for these lower head nozzles shall not extend
beyond the weld plane at the end of the nozzles.
6.2.2.9 Figure 8 provides the requirements and data for in-core instrumentation
nozzle insulation and for heat transfer analyses information.
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6.2.3 Reactor Vessel Insulation Including Lower Head Insulation for ERVC
Operation
6.2.3.1 The ERVC is a function of submerging exterior surface of the reactor vessel
under hypothetical severe accident condition, in order to support avoiding or
delaying reactor vessel melt-through by ERVC.
6.2.3.2 During severe accidents involving reactor cavity flooding (hereinafter called
severe accidents), the insulation shall provide a specified annulus with the outer
surface of the reactor vessel and allow water in the reactor cavity to enter the
bottom of the annulus for cooling of the reactor vessel- The insulation shall also
allow the free discharge of water and steam from the top of the annulus. Free
convection of air to and from this annulus shall be inhibited during normal
operationr
6.2.3.3 For ERVC operation, SCP is used for initial reactor cavity flooding. The SCP
is only manually started and stopped by MCR operators or field operators
after CET temperature exceeds 12007 with allowance of TSC and is
operated until the reactor cavity water level reaches EL114'-4". Also, BAMP
is used for refilling the amount of water that boils by decay power after
initial flooding by SCP.
6.2.3.4 The insulation including each passive cooling water ingression and steam/water
venting assemblies shall be suitable design to perform its required function and
operation under functional, operating, environmental and design conditions
specified in this specification.
6.2.3.5 A passive attribute allowing ingression of water in the reactor cavity into the
space between the insulation and the reactor vessel shall be installed on the
lower head with reactor vessel insulation (see Figure 8). The passive cooling
water ingression device assembly shall be designed and provided by the Supplier.
6-2.3.6 A stearn/water venting assemblies shall be installed on the reactor vessel
insulation at the bottom of the lower streaming shield and shall not interfere with
reactor cavity structure including lower streaming shield and other reactor cavity
components (see Figure 7). The steam/water venting device assembly shall be
designed and provided by the Supplier.
6.2.3.7 Each passive cooling water ingression and steam/water venting assemblies shall
be designed normally closed to prevent an air circulation path through the RV
and an inadvertent operation.
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62.3.8 The insulation for ERVC shall be designed to heat removal from core debris via
boiling on the outside surface of the reactor vessel by passive cooling water
ingression and steam/water venting assemblies when operating with following the
ERVC environmental conditions.
Reactor Vessel Surface Temperature refer to Figure 9
Relative humidity of ambient 100 %
5.2.3.9 The passive cooling water ingression assemblies shall be designed to minimize
the pressure drop and withstand an acceptable pressure drop during ERVC to
permit water inflow to cool the vessel. The maximum total flow rate inside the
insulation space is 1,200 kg/sec.
6.2.3.10 The steam/water venting assemblies shall be designed to withstand an acceptable
pressure drop through the opening during ERVC. The steam/water venting
assembly shall be designed not to buildup pressure inside the insulation space.
6.2.3.11 A minimum gap as shown in Figures 2, 3, 4, 7 and 8 shall be maintained in the
water/steam annulus between reactor vessel sidewall and the insulation for
transient motions during dynamic conditions in the direction of the reactor vessel
during a severe accident The contour of the lower head shall be maintained
during a severe accident.
6.2.3.12 The reactor vessel support column base plate shall not be directly exposed to the
reactor vessel exterior surface due to the enlarged gap and the added attributes
of the reactor vessel insulation for ERVC (see Figure 3) shall meet the
requirements for normal and abnormal operating condition.
6.2.3.13 The reactor vessel insulation support shall retain the configuration of the
insulation, passive cooling water ingression and steam/water venting assemblies
under the maximum buoyancy force imposed by water flooded outside the reactor
vessel insulation in the reactor cavity (see Figure 10).
6.2.3.14 The gap between the RV wall and the RVI at the level of RV shear key and
lower head shall be enlarged to the extent as possible without changing the
thermal and mechanical parameters at the outer surface of the RVI from the
conventional design Practice. The high perfonmance insulation shall be utilized for
the RVI, including the RV lower head insulation.
3L186-FS-DS910 DDS-1 Rev. 05 Page 31 of 56
9-113-Z-404-001C
6.2.3.15 The insulation shall not prevent safety-related systems from performing their
intended functions including during and after design basis accidents. This includes
equipment including, but not limited to, the reactor vessel and connected piping,
the ex-core detectors, and the Emergency Core Cooling System.
6.2.3.16 The design shall permit in-service inspection of the passive cooling water
ingression and steam/water venting assemblies for proper operation. Any
insulation that needs to be removed to perform these inspections shall be readily
removable.
6.2.3.17 The insulation and its supports shall be designed to withstand bounding pressure
differential across the reactor vessel insulation panels during the period that the
reactor vessel is externally flooded with water and the core heat is removed from
the vessel wall by water and generated steam is vented
6.2.3.18 The structural frame supporting the insulation shall be designed to withstand the
bounding severe accident loads while maintaining the flow path. The quick
released buckle fasteners and strikers retaining the insulation panels to the frame
shall be also designed for these load.
6.2.3.19 The total flow area of the passive cooling water assemblies has sufficient margin
to preclude significant pressure drop during ERVC. The flow area for the water
ingression shall be more than 19.0 ft2. Individual passive cooling water channel
shall have a minimum flow area to avoid clogging from any debris in the water
(see Figure 8).
6.2.3.20 The passive cooling water ingression assemblies shall be designed to be opened
by the hydrostatic pressure difference acting on itself following refilling the
reactor cavity. The abnormal operation of the passive attrihites due to HVAC air
flow shall be prohibited (see Figure 4-1).
6.2.3.21 The flow area for venting steam/water during a severe accident shall be more
than 18A0 ft2 . The flow area of steam venting assemblies shall be more than 4.0
fte. (see Figure 7). Individual steam/water venting assembly shall not be
susceptible to clogging from any debris in the steam and water.
6.2-322 The stear/water venting assemblies shall be constructed of light-weight
materials to minimize the force necessary to open and permit flooding and
continued water flow through the opening during ERVC operation.
3L186-FS-DS910 DDS-1 Rev. 05 Page 32 of 56
9-113-Z-404-O0IC
6.2.3.23 The insulation shall meet its functional requirements for the severe accident while
accommodating the hydrostatic and dynamic loads from boiling in the annulus
between the reactor vessel and the insulation during a severe accident. The
pressure variations in the channel between the RPV and the RVI are on the
order of ±2.5 feet of water. The dominant frequency of the pressure variations is
less than 2.5 Hz.
6.2.3.24 The insulation shall maintain the specified annulus with the reactor vessel and
the passive cooling water ingression and steam/water venting assemblies shall
function following the effects of a leak in the inlet, outlet or DVI pipes within the
reactor cavity or a pipe leak/break elsewhere in containment. The maximum
pressure across the insulation panels for this event is 105 psi.
6.2.4 Reactor Vessel Insulation Reouirements to Allow Insulation of the ALMS and
LPMS Sensors and their Covers
6.2.4.1 The reactor vessel shall be insulated in the vicinity of ALMS and LPMS
sensors. The location of ALMS and LPMS sensors is defined by Table 2 and
Table 3, respectively.
6.24.2 Cutouts shall be provided in the insulation to accommodate the ALMS and
LPMS sensor covers.
6.2.4.3 Insulation that covers ALMS and LPMS sensor covers shall be removable to
allow access to the sensors and their covers for maintenance.
6.2.4.4 Insulation in the vicinity of ALMS and LPMS sensor covers shall provide the
clearances specified in Reference 3.2.9.
6.2.4.5 The flange insulation shall be designed not to interfere with ALMS/LPMS
conduits shown on Reference 3.2.14.
6.2.4.6 The dome insulation shall be designed to route ALMS cables shown on
Reference 3.2.14.
6.2.4.7 Insulation of the reactor vessel inlet and outlet nozzles shall be designed to
accommodate the interfaces with the ALMS sensor and its cable shown on
Reference 3.2.15 and 3.2.16.
3L186-FS-DS910 DDS-1 Rev. 05 Page 33 of 56
9-113-Z-404-OO1C
7.0 MATERIAL AND FABRICATION
7.1 Material Requirements
7.1.1 Materials of construction shall be selected such that a neutron fluence of 2 x
1018 n/cm2 (E Ž_ 1 MeV) will not adversely affect insulating properties nor
result in background radiation due to activation.
7.1.2 Materials of construction shall be free from low melting point materials and
alloying constituents. Material made of, or compounds containing aluminum,
zinc, copper and/or lead, shall not be used in the construction of the
insulation.
7.1.3 The insulation's interior and exterior sheathing shall be austenitic stainless
steel. All other materials for reflective insulation shall be austenitic stainless
steel.
7.1.4 Non-metallic insulation shall comply with Reference 3.4.5 and reflective type
insulation shall comply with Reference 3.4.3.
7.1.5 Materials of construction shall not be damaged when wetted by an aqueous
dilute solution (4400 ppm boron as HaBO3) of boric acid and up to 100 ppm
hydrazine with pH 3.8 to 10.6.
7.1.6 Materials of construction shall be non-combustible and shall withstand a
continuous operating temperature of 650'F without degradation of insulating
properties to less than design requirements. Insulation shall maintain integrity
at 1,000F during severe accident.
7.1.7 All suppliers provided insulation supports shall be austenitic stainless steel.
3L186-FS-DS910 DDS-1 Rev. 05 Page 34 of 56
9-113-Z-404-001C
8.0 CLEANING
8.1 Cleaning Requirements
8.1.1 The insulating materials shall be thoroughly cleaned prior to assembly into
panels to the extent that no extraneous dirt or chemical deposits are on the
surfaces. In particular, no leachable halogens are permitted on the insulation
surfaces.
9.0 IDENTIFICATION
9.1 A permanently affixed tag with an easy to read identification or code number
cross referenced to the drawings shall be attached to each piece of insulation.
The method of identification is subject to Purchaser's approval.
10.0 PACKAGING, SHIPPING AND SHIPPING CONTAINERS
10.1 Packaging Requirements
10.1.1 The insulation shall be packaged and shipped in accordance with
requirements for Level C components of Reference 3.4.4.
10.1.2 Fasteners and other hardware may be packed in a separate container, or may
be attached to the insulation. If the latter method is used, the fasteners and
other hardware shall be affixed to the insulation in such a manner to prevent
their movement during transport.
10.2 Shipping Requirements
10.2.1 The method of shipping will be stated in the purchase order.
10.3 Shipping Container Requirements
10.3.1 The insulation shall be packaged in Purchaser approved shipping containers
which protect the insulation from damage. The Supplier's written
recommendations for loading, handling, and unloading shall be included in a
waterproof envelope attached to the container.
3L186-FS-DS910 DDS-1 Rev. 05 Page 35 of 56
9-113-Z-404-001C
Table 1
SUPPLIER DOCUMENT SUBMITTAL SCHEDULE I
COMPONENT
SUPPLIER
PURCHASE ORDER NO. P.O. DATE
Document Req'dPer Si)ec.(Para.)
*Supplier' s
Req'd
Submittal Date
Purchaser's
Approval/Comments
DateDocument Description
* See Paragraph 5-1.1.5.2
3L186-FS-DS910 DDS-1 Rev. 05 Page 36 of 56
9-113-Z-404-001C
Table 2
LPMS SENSOR LOCATIONS ON THE REACTOR VESSEL
LOCATION REQUIRE ID COORDINATES SENSOR MOUNTING LOCATION_____________402)
0'3
)
1 V-101 300 50 Between flange circle and lift rig lugsClosure 1 V-102 300 1250 Between flange circle and lift rig lugs
Head1 V-103 300 2450 Between flange circle and lift rig lugs
1 V-104 40' 300 Outside ICI nozzle circle
Lower 1 V-105 400 1500 Outside ICI nozzle circle
1 V-106 400 270* Outside ICI nozzle circle
Notes (1) Specific locations will depend on component design.
(2) Reactor Vessel tangent line is the 00 reference for the Reactor Vessel
Lower Head channels, and the mating surface is the 00 reference for the
Reactor Vessel Closure Head Channels.
(3) RCS hot leg 1 axis is 0* reference.
00Closu•r H•ad --
V-103
V-105
1800
3LI86-FS-DS910 DDS-1 Rev. 05 Page 37 of 56
9-113-Z-404-001C
Table 3
ALMS SENSOR LOCATIONS ON THE REACTOR VESSEL
NUMBER COORDINATES-()LOCATION ID SENSOR MOUNTING LOCATION
1 U-101 44A' 82' Between CEDM nozzlesý4), No. 71 & 95
Closure I U-102 44.4" 202" Between CEDM nozzles(4), No. 66 & 98
Head )1 U-103 44.4' 322" Between CEDM nozzles , No. 61 & 77
1 U-104 65" 15' Between ICI nozzles, No. 48 & 56
Head 1 U-105 65" 135" Between ICI nozzles, No. 13 & 18
1 U-106 65 255* Between ICI nozzles, No. 24 & 33
Notes (1)
(2)
(3)
(4)
Specific locations will depend on component design.
Reactor Vessel tangent line is the 00 reference for
Lower Head channels, and the mating surface is the
Reactor Vessel Closure Head Channels.
RCS hot leg loop 1 axis is 00 reference.
CEDM nozzle numbers are shown in Reference 3.2.5.
the Reactor Vessel0° reference for the
-90,
00.Lower Head
'. • •~~U-104 •)''
U-105 U- 10
U-106
3LI86-FS-DS910 DDS-1 Rev. 05 Page 38 of 56
9-113-Z-404-001C
FIGURE 1
CEDM NOZZLE THERMAL AND INSULATION DATA
COOLING AIR CONDITION:
Temperature = 95-F to 155-F (For Normal Operation)
= 83F to 143"F (For Upset Condition*)
Velocity = 27 ft/sec to 30 ftsec
= 40 ftlsec to 45 ft/sec
(For Normal Operation)
(For Upset Condition")
-C>
CEOM "THERMAL WRAP
CLOTH GASKET" INSULATION
CEOM NOZZLE (TYPICAL)
RV HEAD INSULATION
RV HEAD
NO GAP HERE. THE GAPSHOWN ONLY FOR CLARIFY
CEDM "THERMAL WARP-"CLOTH GASKET' INSULATION
- CEDM NOZZLE (TYPICAL)
* Cooling air flow rates for Normal Operation and
and 1200 SCFM per CEDM, respectively.
** Upset condition is defined as an overcooling event
than twelve(12) times per year.
Upset Condition are 800 SCFM
and assumed to occur not more
*** CEDM "Thermal Wrap Cloth Gasket" shall be installed to prevent air leakage, and
shall be attached to removable insulation.
3L186-FS-DS910 DDS-1 Rev. 05 Page 39 of 56
9-113-Z-404-001C
FIGURE 2
RV SUPPORT INSULATION REQUIREMENTS
REFLECTIVE INSULATIONOR EQUIVALENT HIG-IEFFICIENCY INSULATIONIS REQUIRED HERE TOMINIMIZE HEAT TRANSFERFROM RV I*LL TO St"P(RT
FLECI VEINSULAT ION
OF R.V. REF
3LI86-FS-DS910 DDS-1 Rev. 05 Page 40 of 56
9-113-Z-404-001C
FIGURE 2
RV SUPPORT INSULATION REQUIREMENTS (Cont'd)
7 1/2' MINMtEARANC
SECTION B--B
3L186-FS-DS910 DDS-1 Rev. 05 Page 41 of 56
9-113-Z-404-001C
FIGURE 2
RV SUPPORT INSULATION REQUIREMENTS (Cont'd)
NOTE: DIMENSION "A" TO SUIT A/E STfRUCTIIR
SECTION1 C--C
3L186-FS-DS910 DDS- RRev. 05 Page 42 of 56
9-113-Z-404-001C
FIGURE 3
RV SHEAR KEY INSULATION REQUIREMENTS
- MSAafl Emm) ON"IMH. SUMMACI OVOLMIMX U 0FA O /MH
FA
RBF
Notes: 1) 2.6"rnin. clearance the cold condition
2" min. clearance the severe accident condition
2) Adequate space shall be provided to withdraw and install the lower
expansion plate assembly during HFT.
3L186-FS-DS910 DDS-1 Rev. 05 Page 43 of 56
9-113-Z-404-001C
FIGURE 3
RV SHEAR KEY INSULATION REQUIREMENTS (Cont'd)
I1NSULA'11OD RgU;I INTM ATME TO KEY.HEATRM(MMMM I.
SECTION A-A
Notes: 1) Thermal Conductivity, K=0.02 Btu/hr-ft-TF Max.
2) 2.6"min. clearance the cold condition
2" min. clearance : the severe accident condition
3) Adequate space shall be provided to withdraw and install the lower
expansion plate assembly during HFT. I
3L186-FS-DS910 DDS-I Rev. 05 Page 44 of 56
9-113-Z-404-OO1C
FIGURE 4-1
REACTOR CAVITY STRUCTURE REQUIREMENTS
( KEY ELEVATION )
AVERAGE AVERAGE
SECT. AMi TEMP.
___ _ (FPM) __
1 73 115
2 75 472
3 77 424
4 85 97
5 93 547
95 46 Nozzlei695 46 Wall
7 97 146
_8 120 89
3L186-FS-DS910 DDS-1 Rev. 05 Page 45 of 56
9-1 13-Z-404-001C
FIGURE 4 - 2
REACTOR CAVITY STRUCTURE REQUIREMENTS
(UPPER & LOWER STREAMING SHIELD)
UPPERSTREAMINGSHIELD
3.44"R .
• ~LOWERlSTREAMINGSHIELD
4.3" REF.
D7 ýC---LOCKAGE OF 50%/
NOTE : Nozzles are omitted for easy understanding.
3LI86-FS-DS910 DDS-1 Rev. 05 Page 46 of 56
9-113-Z-404-001C
FIGURE 4 - 3
REACTOR CAVITY STRUCTURE REQUIREMENTS
(LOWER HEAD INSULATION SUPPORT EMBEDMENT PLATE)
3L186-FS-DS910 DDS-1 Rev. 05 Page 47 of 56
9-113-Z-404-001C
FIGURE 5
THERMAL AND INSULATION DATA OF THE
INTEGRATED HEAD ASSEMBLY AND DOME AREACEDM
Baffle / Plenum Plate
RV Mating SurfaceRV
(Units: inch)
NOTES:() Portion of bottom ring flange and cooling shroud shell shall be included in
heat transfer analysis of RV head and head pads. For 1HA geometry, see
References 3.2.1 and 3.2.12.
(2) Bottom ring flange and cooling shroud shell materials: ASTM A588
(3) Cooling air conditions* inside reactor vessel head area under CEDM Plenum
Plate:Ambient Temp. = 60TF to 120TF (For Normal Operation)
= 60-F to 120"F (For Upset Condition')
Temp. = 95TF to 155F (For Normal Operation)
83TF to 143'F (For Upset Condition-)
Velocity = 27 ft/sec to 30 ft/sec (For Normal Operation)
= 40 ft/sec to 45 ft/sec (For Upset Condition-)
(4) The clearance shall be maintained during 60 years (see Paragraph 6.21.7).
(5) The insulation panel shall be provided with high performance insulation
rnaterial. The thickness of insulation panel shall be determined by the Supplier.
* Cooling air flow rates for Normal Operation and Upset Condition are 800
SCFM and 1200 SCFM per CEDM, respectively.
** Upset condition is defined as an overcooling event and assumed to occur
not more than twelve(12) times per year-
3L186-FS-DS910 DDS-1 Rev. 05 Page 48 of 56
9-113-Z-404-001C
FIGURE 6
REACTOR CAVITY
PERMANENT POOL SEAL ASSEMBLY ENVELOPE
2 K 4..
VESSEL RANE
sa0231.00±.06"TO OECR DIMeTEROF VESSEL FLANE * AS-WILT DIM-CSION REQUIRED
MLI86-FS-DS910 DDS-1 Rev. 05 Page 49 of 56
9-113-Z-404-001C
FIGURE 7
RV SHELL AND STEAM/WATER VENTING PORT REQMIREMENTS
- F- > EL. NOZZLE
102.825" R REF
I EL. 114'-4"
R.V.WALL
WATERVENT I NGDEV ICEPORTS
D
- EL. 111' (typical)
-)
101.275" R REF
3L186-FS-DS910 DDS-1 Rev. 05 Page 50 of 56
9-113-Z-404-001C
FIGURE 7
RV SHELL AND STEAM/WATER VENTING PORT REQUIREMENTS (CONT'D)
61ISO,
I INATION
•ITINB, -DEVICE MW3
SECT1ON 0-0
The angles marked with 4 are references.
3LI86-FS-DS910 DDS-1 Rev. 05 Page 51 of 56
9-113-Z-404-OO1C
FIGURE 7
RV SHELL AND STEAMIWATER VENTING PORT REQU-IRME (CONT'D)
VESSEL
MIN. 1.0' REF.
suEMVWAiowr.
3L186-FS-DS910 DDS-1 Rev. 05 Page 52 of 56
9-113-Z-404-001C
FIGURE 8
ICI NOZZME THERMAL, INSUATION AND
PASSIVE COOLING WATER INGRESSION PORT REQMUIEENTS
-INSLILAT I ON
IId NOZZE(TYP ICAL)
COOLING AIR:TII = 75-77 =FVELOCITY = 7.1-7.9 ft/sew
SECTIONS 60' -240' & 1200 -300°
ICI NIOZZE(TYP I CL)
PASSIVECOLI NO RATER
INWMEIONPORT(TYP ICAL)
HIGHNPIATIlt.WTION
3L186-FS-DS910 DDS-1 Rev. 05 Page 53 of 56
9-113-Z-404-001C
FIGURE 8
ICI NOZZLE THERMAL. INSUlATION AND
PASSIVE COOLING WATER INGRESSION PORT REOUIEMETS (CONT-D)
RV WALL
I NSULAT ION
IIWSS IONPOWl_(TYP ICAL)
SECTION E-E
3L186-FS-DS910 DDS-I Rev. 05 Page 54 of 56
9-113-Z-404-001C
FIGURE 9
RV WALL TEMPERATURE REQUIREAMT FOR IVR-ERVC
HHc"ox
SeCIM5
tEC-43
CENTER ELEVATION TEMPERATURE REMARKFROM BOTTOM (INCH) (F) (CC)
1 1.15 2258 1237
2 10.17 2132 1167
3 27.34 1916 1047
4 50.97 1286 697
5 78.75 674 357
6 12327 602 317
7 154.62 602 317
8 185.97 638 337
9 217.32 620 327
10 248.67 602 307
INLET (COLD LEG) Nozzle 674 357
OUTLET (HOT LEG) Nozzle 1628 887
Maximum Reactor Vessel Temperature Just Before Vessel Breach
3LI86-FS-DS910 DDS-1 Rev. 05 Page 55 of 56
9-113-Z-404-001C
FIGURE 10
REACTOR CAVITY GEOMETRY
3L186-FS-DS910 DDS-1 Rev. 05 Page 56 of 56
9-113-Z-404-001C
APPENDIX A
OUTLINE/INTERFACE DRAWING REQUIREMENTS
1.0 Minimum information that is to be included on the Outline/Interface drawings
shall be as detailed below.
1.1 All drawings shall be identified by the form of the drawing title box and
with at least the pertinent information as required by purchase specification.
1.2 OVERALL DIMENSIONS OF EQUIPMENT
These dimensions include extended structures or appendages that make up
the assembled equipment. Pull space and/or any required clearances around
the equipment shall also be shown. Side and end views shall be shown.
1.3 TOLERANCES
All dimensions are to be provided with their tolerances defined. These
tolerances shall be defined by table, or identified directly to the dimension
intended.
1.4 THE WEIGHTS AND LOCATIONS OF EQUIPMENT CENTER OF
GRAVITY
The weight and location of the component dry center of gravity shall be
defined. The center of gravity and weight of any major identifiable
subassembly or component shall be shown on two views so that its location
is defined in all three global directions-
1.5 OTHER REQUIREMENTS
Drawings shall include the following additional information:
a) Bill of Materials (B/M)
1) Drawing Item Number
2) Name of Part
3) Quantity
Appendix A
3L186-FS-DS910 DDS-1 Rev. 05 Page Al of A2
9-113-Z-404-001C
4)
5)
6)
Material
Material Specification (As required by Equipment Specification)
Sizes, Heat Treatments, Model Nos., Identification of all accessories,
threaded fasteners, etc., if applicable.
b) Outline and Assembly
1) Cross section of equipment identifying each item number as defined
by B/M
2) All welds, including hardfacing and indicating weld type, joint design
and non-destructive testing examination
3) All locking devices
4) Torque of all fasteners and other threaded connections (also indicate
lubricants used as applicable)
5) Facsimile of nameplate as defined by Reference 3.3.1
6) Revision block listing all revisions to drawing.
7) All supports and embedments requirements.
Appendix A
3L186-FS-DS910 DDS-1 Rev. 05 Page A2 of A2
9-113-Z-404-OOIC
APPENDIX B
SEISMIC, BLPB AND IRWST DISCHARGE RESPONSE SPECTRA
This Appendix contains response spectra of seismic, BLPB and IRWST
discharge loads for the RVI
Appendix B
3L186-FS-DS910 DDS-1 Rev. 05 Page B1 of BlO
9-113-Z-404-001C
0
H
10
1
0.1 I;)
FREQUENCY (CPS)
RV COMPOSITE X-DIRh.18 2t DA"PI1
SgN 34 DDS-1 SM RESPONSE SPEC-TRA
Appendix B
-DS910 DDS-1 Rev. 05 Page B2 of B103LI86-FS
9-113-Z-404-OO1C
0H
'i-i
C-)
10
I0
1
0.i.
FREQUMCY (CPS)
RV CMCPOSITE Y-DIR (VTj 2% DAMP1NG
BElO 3&4 IA-1 SM REBPONBE SPECTRA
Appendix B
S-DS910 DDS-1 Rev. 05 Page B3 of B103L186-F
9-113-Z-404-001C
100
100-
H•
1
0.1
FREQUENCY ICPS)
RV COIIPOSXTE Z-DIR (B") DM
rnei A4 WS-1 RM RBSPOKOZ 8PECTPA
Appendix BPage B4 of B103L186-FS-DS910 DDS-1 Rev. 05
9-113-Z-404-001C
H4L)
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I II
.....' I i ,, 4.. .
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. I
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FREQUENCY (CP3)
7?ý,T A-:7-
Appendix B
3LI86-FS-DS910 DDS-1 Rev. 05 Page B5 of B10
9-113-Z-404-OO1C
.1.)
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Appendix B
3L186-FS-DS910 DDS-1 Rev. 05 Page B6 of B10
9-113-Z-404-001C
KILI4
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I
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S *11T-11~ . .V4i
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FREQUEN1CY (CPS)
I . ~ f... . . .. . . . .. .. ... . .. . ... .. .. L.. . .....
i :v .er;Ž:.- .. ( -1 oc : -.ilx E..••€ .• V r.T.F'S•.:-SS77 •,T)-.E tr-A 7C..- AT;T'7£•' :A 3I
Appendix BPage B7 of BIO
3LI86-FS-DS910 DDS-I Rev. 05
9-113-Z-404-001C
I -- T - -- - ~T T I~~1 r7T. I1
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FREQUENCY (CPS)
,F . DZ$w -L-.T WS-
Appendix B
3L186-FS-DS910 DDS-1 Rev. 05 Page B8 of B1O
9-113-Z-404-OO1C
I-.
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Appendix BPage B9 of B103L186-FS-DS910 DDS-1 Rev. 05
9-113-Z-404-OO1C
I.e
i-1
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Appendix BPage B1O of B1O3L186-FS-DS910 DDS-1 Rev. 05
ALARA DESIGN/REVIEW CHECKLIST
Docmment Tiltle DESIGN SPECIFICATIONFORREACTOR VESSEL INSULATION
Design Document No. 3L186-FS-DS910 Revision No. 05
A GENERAL
1 Equipment, components and parts are reliable and of high OK
interity to minimize the necessity and frequency of
maintenance.
2 Past operating history and experience with similar componernts OK
have been considered in the equipment selection process.
3 Alternate equipment and process designs have been considered to OK
minimize occupational radiation exposure.
4 Unnecessary equipment and instrumentation has not been included OK
in the design.
5 Access is provided for in-service inspection and the equipment OK
design minimizes the requirements for in-service inspection.
6 Radiation shieldingrequirements consider the contained OK
radiation source of the equipment and requirements for
maintenance.
7 Remote control,. semi-remote control, and/or use of extensions OK
features are utilized, whereas practical, to reduce the
residence time of workers at the radioactive areas.
8 Components. containing the reactor coolant are designed to OK
facilitate ease of removal for maintenance and/or repair.
9 Easy access and sufficient work areas for radiation workers are OK
considered in the design.
10 Sufficient space is provided around equipment disassembly and OK
laydown.
11 Space is provided in low radiation areas close to the equipment OK
for maintenance of subassembl ies removed from equipment.
12 Equipment surfaces contacting the reactor coolant or refuel ing OK
water are free of crevices to minimize the accumulation of crud.
13 Radioactive fluid bearing equipment is equipped with drains and OK
vents to completely drain the equi-pment f!or maintenance.
1 of 6
ALARA DESIGN/REVIEW CHECKLIST
Document Tiltle DESIGN SPECIFICATIONFORREACTOR VESSEL INSULATION
Design Document No. 3L186-FS-DS91O Revision No. 05
14 The use of pipe snubbers and restraints are minimized through NA
the app! ication of Leak-Before-Break technology.
15 Hydraulic snubbers are used only in locations that are not NA
appropriate for the use of mechanical snubbers.
16 Equipment, such as pumps and valves, that are removed for NA
service are equipped with flanged connections for removal.
17 Robotics, remote operated equipment and other automated NA
equipment are utilized, whenever practical, to perform
maintenance, inspection and surveillance tasks in high radiation
areas.
18 Quick-removal type insulation designed for reuse is utilized on OK
locations on the reactor coolant system piping and equipment
where external access is required for in-service inspection.
19 Radioactive equipment is separated from non-radioactive NA
equ i pment.
20 Redundant radioactive equipment or trains of radioactive NA
equipment are separated or shielded from each other.
21 Active radioactive equipment is separated from passive OK
radioactive equipment.
B MATERIAL SELECTION
1 Material selection has considered minimization of cobalt and OK
nickel content of the equipment surfaces in contact with the
reactor coolant to reduce the formation of crud.
2 Corrosion-resistant material, where ever practical, is selected OK
for the equipment in contact with the reactor coolant.
3 Material selection has considered the use of chemical OK
decontamination of fluid containing components.
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ALARA DESIGN/REVIEW CHECKLIST
Document Tiltle DESIGN SPECIFICATIONFORREACTOR VESSEL INSULATION
Design Document No. 3L186-FS-DS91O Revision No. 05
4 Non-corrosion resistant surfaces are coated with a tightly OK
adherent, non-porous coating to allow easy decontamination of
the equIpment.
5 Material selection, particularly for non-metal components, OK
considers both the radiation exposure and contained fluid to
minimize maintenance..
C VALVES
1 Valves in radioactive systems that are adjusted for process NA
control are remotely operated.
2 Valves are low-leakage, packless types with backseats. NA
3 Where packless valves can not be used, reactor coolant leakage NA
is minimized by use of double stem packings, valve packing
glands are capable of adjusting the packing compression, and the
valve body is equipped to collect stem leakage.
4 Valve design minimizes the seat wear. NA
D ION EXCHANGERS
1 Remote controlled flushing of ion exchangers is used for the NA
removal of spent resin to radwaste system.
2 Ion exchanger manways are easily accessible. Minimal disassembly NA
is required for easy. removal of internal components through
manways.
3 The fresh resin ion exchanger inlet is designed to extend into a NA
low radiation area above the shielded compartment housing of the
ion exchanger.
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ALARA DESIGN/REVIEW CHECKLIST
£ocument Ti tle DESIGN SPECIFICATIONFORREACTOR VESSEL INSULATION
Design Document No. 3L186-FS-DS910 Revision No. 05
4 The resin traps downstream of ion exchangers are provided with a NA
remote backwash capability to permit the resin traps to be
cleaned remotely..
E HEAT EXCHANGERS
1 Heat. exchanger Internals.are readily serviceable with a minimum NA
for disassembly.
2 Fluid velocities minimize deposition of crud. NA
F FILTERS
1 Filter housings are provided with vent connections and are NA
designed for complete drainage.
2 Remote removal of the filter elements is permitted in the filter NA
housing and cartridge design.
3 Submicron mesh filters are used in letdown system, and NA
purification of seal water for reactor coolant system.
4 Standardizedtechniques for filter handling are used throughout NA
the plant.
G TANKS
1 Tanks are vented to either the gas collection header or the gas NA
surge header to facilitate removal of potentially radioactive
gases during maintenance,
2 Non-pressurized tanks are provided with overflows, routed to a NA
floor drain or other suitable collection point tb avoidradioactive fluids spilling to the floor, or ground.
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ALARA DESIGN/REVIEW CHECKLIST
Dociment Tiltle DESIGN SPECIFICATIONFORREACTOR VESSEL INSULATION
Design Document No. 3L186-FS-DS910 Revision No. 05
3 Tanks have sloped bottoms, flushing connections and are NA
completely drainable.
H WATER CHEMISTRY
Reactor water makeup and reactor coolant water chemistry reduce NA
the potential generation Of crud during start-up, poweroperation, and shutdown conditions..
2 The CVCS has the facil ities for hydrazine injection into the NA
reactor coolant and the capacity for increased filtration rates
during hot shutdown conditions.
REFUELING
1 The fuel handling system provides adequate shielding to NA
personnel during fuel handling.
2 The NSSS equipment-minimizes task duration and personnel NA
requirements during reactor head removal/installation and
refueling.
J INSTRUMENTATION
1 Instruments required for process control are located in a low NA
radiation area.
2 Process instrumentation can be isolated for maintenance. NA
3 Control panels are located in low radiation areas. NA
4 Relay cabinets, multiplexers and instrument racks are located in NA
low radiation zones.
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ALARA DESIGN/REVIEW CHECKLIST
Document Tiltie : DESIGN SPECIFICATIONFORREACTOR VESSEL INSULATION
Design Document No. : 3L186-FS-DS910 Revision No. : 05
K DECOMMISSIONING
1 Design features which possibly reduce the radiation dose rates
during decommissioning are considered in NSSS designs.
L COMMENTS/REMARKS(This item describes the additional ALARA implementation not
Included above ALARA review checklist.)
None
NA
Chang Joon Bae hA½6a~V02 01/02/2012
ALARA Desiqn Reviewer (Name, Sianature. Date)
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