ichn p co., · 5.5 documents required to be submitted for approval prior to 19 material release 5.6...

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


Editorial Correction


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


Fabrication Release


Release for Shipment


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


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


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.


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).


Information provided for material ordering and sizing purposes and for

preliminary calculations, based on assumptions requiring confirmation.


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.


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


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


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)


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


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:


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.


9-113-Z-404-001C

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.


9-113-Z-404-OOIC

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.


9-113-Z-404-001C

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.)


9-113-Z-404-001C

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


9-113-Z-404-OO1C

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

3LI86-FS-DS910 DDS-1 Rev. 05 Page 20 of 56

9-113-Z-404-OO1C

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.


9-113-Z-404-001C

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


9-113-Z-404-OO1C

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


9-113-Z-404-OO1C

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.

3L186-FS-DS910 DDS-I Rev. 05 Page 24 of 56

9-113-Z-404-OO1C

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.

3L186-FS-DS910 DDS-1 Rev. 05 Page 25of 56

-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


9-113-Z-404-001C

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

3L186-FS-DS910 DDS-1 Rev. 05 Page 2'7 of 56

9-113-Z-404-OO1C

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).


9-113-Z-404-OO1C

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.


9-113-Z-404-001C

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.


9-113-Z-404-001C

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.


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.


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.


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.


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.


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


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


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


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.


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


9-113-Z-404-001C

FIGURE 2

RV SUPPORT INSULATION REQUIREMENTS (Cont'd)

7 1/2' MINMtEARANC

SECTION B--B


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.


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


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


9-1 13-Z-404-001C

FIGURE 4 - 2


(UPPER & LOWER STREAMING SHIELD)

UPPERSTREAMINGSHIELD

3.44"R .

• ~LOWERlSTREAMINGSHIELD

4.3" REF.

D7 ýC---LOCKAGE OF 50%/

NOTE : Nozzles are omitted for easy understanding.


9-113-Z-404-001C

FIGURE 4 - 3


(LOWER HEAD INSULATION SUPPORT EMBEDMENT PLATE)


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-


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


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.


9-113-Z-404-OO1C

FIGURE 7

RV SHELL AND STEAMIWATER VENTING PORT REQU-IRME (CONT'D)

VESSEL

MIN. 1.0' REF.

suEMVWAiowr.


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


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


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


9-113-Z-404-001C

FIGURE 10

REACTOR CAVITY GEOMETRY


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 1

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.....' I i ,, 4.. .

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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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to

I

K) .2.

S *11T-11~ . .V4i

±~. j i,'j:! j fll zŽlI- I: ]' --41 1" '

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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

.11 -I-I-

Pt91-4

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FREQUENCY (CPS)

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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

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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


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.

2 of 6


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.

3 of 6


£ocument Ti tle DESIGN SPECIFICATIONFORREACTOR VESSEL INSULATION


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.

4 of 6


Dociment Tiltle DESIGN SPECIFICATIONFORREACTOR VESSEL INSULATION


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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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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