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Rev 0 to Inservice Insp Program Plan for Second Insp Interval,Vol 1,Inservice Insp Program Plan for Components & Component Supports,880606-980606. W/92 Oversize Drawings
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Site:	North Anna
Issue date:	03/31/1988
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
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-VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM PLAN FOR THE SECOND INSPECTION INTERVAL VOLUME 1 i

INSERVICE INSPECTION PROGRAM PLAN FOR COMPONENTS AND COMPONENT SUPPORTS REVISION O MARCH 1988 INTERVAL 2 JUNE 6, 1988 - JUNE 6, 1998 O

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A PROGRAM ASSIGNMENT Copy No. UNCONTROLLED This copy of the North Anna Unit 1 Second Interval Inservice Inspection Program Plan has been assigned to:

UNCONTROLLED 1

This program plan is the property of Virginia Power, and snall be returned to the Supervisor-Inservice Inspection Programs, Nuclear Operations 1epartment, Richmond General Office, in the event the employee terminates his (mployment, is reassigned outside his present location, or upon the regtest of the Supervisor-Inservice Inspection Programs, Nuclear Operations Department.

O, This program plan shall be maintained and updated by the person Llose name appears above as revisions are issued.

The date the revision is inserted shall be recorded and initialed on the revision sheet by the person making the entry.

The usefulness of this manual is dependent upon it being maintained current.

Periodic inspections of selected manuals will be conducted to verify that all manuals are current.

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N1-01A i

Rev. O March 6, 1988

VIRGINIA ELECTRIC AND POWER COMPANY q

NORTH ANNA POWER STATION UNIT 1 4

INSERVICE INSPECTION PROGRAM PLAN SECOND INSPECTION INTERVAL JUNE 6, 1988 - JUNE 6, 1998 REVISION O DISTRIBUTION RECORD DISTRIBUTION DATE DISTRIBUTION DATE NO.

ENTERED INITIAL NO.

ENTERED INITIAL 1

21 2

22 3

23 4

24 5

25 6

26 7

27 8

28 9

29 10 30 11 31 12 32 13 33 14 34 15 35 16 36 17 37 18 38 19 39 20 40 Future distributions to this program plan will be accompanied by two copies of

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the distribution memo, one of which is to be returned per instructions thereon, and the other one is to be filed sequentially behind this page giving you a record of the contents of each distribution.

11 N1-000 Rev. O m.

farr4h 6n 1@88

'l TABLE OF CONTENTS i

l 1

l SECTION TITLE PAGE l

1 Assignment l

11 Distribution Record iii Table of Contents iv Abstract i

vi List of Drawings 1

Introduction 2

Inservice Inspection Program Plan for Components i

3 Inservice Inspection Program Plan for Component Supports 4

System Pressure Tests Program Plan i

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i N1-000 Rev. O March 6, 1988

ABSTRACT VIRGINIA ELECTRIC AND POWER C0KPANY

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NORTH ANNA POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM PLAN SECOND INSPECTION INTERVAL JUNE 6, 1988 TO JUNE 6, 1998 In accordance with 10CFR50.55a dated January 1, 1987, the North Anna Unit 1 Inservice Inspection Program (ISI) was updated to meet the requirements of ASME Section XI, 1983 Edition with Addenda through Summer 1983.

Specific relief requests are in accordance with 10CFR50.55a(g)(5)(iii).

The interval to which this program is applicable vill commence on June 6, 1988 and will end on June 6, 1998.

This program plan is divided into two volumes.

Volume 1 contains the Inservice Inspection Program Plan and Volume 2 contains the Inservice Testing Program Plan.

The Inservice Inspection Program Plan was developed by employing the guidelines of 10CFR50, Regulatory Guide 1.26 Revision 3, ANSI N18.2 - 1973, ANSI N18.2a - 1975 and NUREG-0800 (Standard Review Plan 3.2.2 - Revision 1) in conjunction with the System Quality Group Classification Section of the North Anna Power Station UFSAR(3.2.2).

Quality Groups A, B, and C as discussed in Regulatory Guide 1.26 are considered the same as ISI Classes 1, 2, and 3 for purposes of this program plan.

O

The List of ISI Classification Boundary Drawings (see pages vi-viii) identifies the Scope of the ISI Program.

Specific implementation of the ISI Program Plan for subsections IWB, IWC, IWD and IWF of ASME Section XI is detailed on the Classification Boundary Drawing Legend and Symbols Drawing (11715-CBM-L&S-2) and the coded ISI Classification Boundary Drawings (CBDs). Components other than piping (e.g. heat exchangers,

tanks, pumps, compressors and other vessels) are classified for ISI examinations to the most restrictive examination requirements of the piping attached.

For example, if a vessel has ISI Class 2A, 2B and 3B lines attached, the component will be examined to the ISI Class 2A requirement.

Exceptions to this convention are as follows:

l Component ISI Classification Code l

1-CH-E-1 2F 1-CH-E-2 2A 1-CH-E-3 2A 1-CH-E-4 (tube side) 2A 1-CH-E-4 (shell side) 3A 1-CH-FL-2 2F 1-CH-FL-4A 2A 1-CH-FL-4B 2A 1-CH-TK-2 2F 1-QS-TK-1 2F iv N1-000 Rev. 0 0

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The Program Plan is organized as follows:

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Section 1:

Introduces the Inservice Inspection Program Plan.

Section 2: Describes the Class 1,

2, and 3 Component Inservice Inspection Program developed in accordance with Subsection. IWB, IWC, and IND of ASME Section XI.

The ISI Classificatio.; Boundary Drawings define the scope of this program.

All components within these boundaries are subject to Section XI examination, except where exempted in Subsection 2.2.2 or where relief from examination is noted in Subsection 2.6.

Section 3: Describes the Inservice Inspection Program for Component Supports.

Component Supports within the boundaries defined by the ISI Classification Boundary Drawings are subject to Section XI examination as detailed in 11715-CBM-L&S-2 except where exempted in Subsection 3.3 or where relief from examination is noted in Subsection 3.5.

Hydraulic shock suppressors on Class 1, 2 and 3 systems will be examined in accordance with station Technical Specifications, j

1 Section 4: Describes the Inservice System Pressure Test Program.

All pressure retaining components within the boun,daries defined by the ISI Classification Boundary Drawings are subject to pressure testing except where relief is noted in Section 4.4.

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v N1-000 Rev. O March 6, 1988

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l NMTH AO.A. UNIT 1 !$1 CLAS$1FICATION 80UNDARY ORAWINGS m

ORAVING SHEET ;RAk t WJ CLASS CLASS CLASS NUMBER NUMBER TITLf:

1 2

3 11715 CBB 006A 1073 AI A Cot'2 f MG & PURGING SYSTEM 2

11715 CBB 1028 10F1 INT S!.OR FIRE PROTECTION & HOSE RACK SYS 2

11715 CBM 070A 10F3 Malt STEAM SYSTEM 3

30F3 MA M STEAM SYSTEM 3

l 11715 CBM 070s 1373 MAIN STEAM SYSTEM 2

3 2CF3 MAIN STEAM SYSTEM 2

3 30F3 MAIN STEAM SYSTEM 2

3

]

11715 CBM 072A 2483 AUXILIART STEAM & Alt REMOVAL SYSTEM 2

11715 CBM 074A 10F3 FEEDWATER SYSTEM 2

3 30F3 FEE 0 WATER SYSTEM 3

11715 CBM 078A 10F4 SERVICE n'ATER SYSTEM 3

30F4 SERVICE NATER SYSTEM 3

40F4 SERVICE WATER SYSTEM 3

11715 CBM 0784 10F4 SERVICE WATER SYSTEM 2

3 20F4 SERVICE WATER SYSTEM 3

11715 CBM 078C 1072 SERVICE WATER SYSTEM 3

20F2 SERVICE WATER SYSTEM 3

11715 CBM 0784 10F2 SERVICE V4TER SYSTEM 3

20F2 SF*.< ICE WATER SYSTEM 3

11715 CBM 079A 10F3 CO#0NENT COOLING WATER SYSTEM 3

20F3 CaePONENT COOLING WATER SYSTEM 3

30F3 CCMPONENT COOLING WATER SYSTEM 3

11715 C8M 0798 10F5 COMPowtNT COOLING WATER SYSTEM 2

1 20F5 COMPCNENT COOLING WATER SYSTEM 2

3 30F5 CCMPOWENT COOLING WATER SYSTEM 2

3 40F5 CGIPOWENT COOLING WATER SYSTEM 2

3 5075 CCMPOWENT COOLING WATER SYSTEM 3

11715 CsM 079C 10F5 CGEP0 MENT COOLING WATER SYSTEM 3

3075 CGePONENT COOLING WATER SYSTEM 3

)

40F5 COMPONENT COOLING WATER SYSTEM 3

5075 CCMPONENT COOLING WATER SYSTEM 3

11715 CBM 0790 40F5 CCMPOWENT COOLING WATER SYSTEM 2

11715 CBM 082A 10F3 COMPRESSED Alt SYSTEM 2

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Rev. O vi March 6, 1988

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NORTH ANNA UWlf 1 !$! CLASS!FICAf!CN B M DARY ORAWINGS m

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(j ORAW!kG SHEET CRAWING CLASS CLASS CLASS NUMBER NUMBER TITLE 1

2 3

11715 CBM 082C 10F2 COMPRESSED A!R SYSTEM 2

11715 CSM 082F 10F1 COMPRESSED AIR SYSTEM 2

11715 CBM 082N 10F3 CCMPRESSED AIR SYSTEM 2

30F3 COMPRESSED AIR SYSTEM 2

11715 CCM 088A 10F4 FUEL PIT CLEANING & REFUELING PURIF SYS 2

3 20F4 FUEL Pif CLEANING & REFUELING PURIF SYS 2

40F4 FUEL PIT CLEANING & REFUEL!kG PURIF SYS 3

11715 CSM 0898 30F4 SAMPLING SYSTEM 2

11715 C8M 0890 10F1 SAMPLING SYSTEM 1

2 11715 C8M 090A 10F2 VENT & CRAIN SYSTEM 2

11715 C9M 090C 10F3 VENT & CRAIN SYSTEM 2

30F3 V!NT & CRAIN SYSTEM 1

2 11715 CSM 051A 10F4 CONT outhCN & RECIRC SDRAY SU9 SYC 2

3 (A

20F4 CONT CUENCH & RECIRC SPRAY SUB SYS 2

30F4 CONT QUENCH & RECIRC SPRAY SUS SYS 2

40F4 CONT CUENCN & RECIRC SPRAY SUS SYS 2

11715 CBM 091B 10F1 CONT QUENCH & RECIRC SPPAY SUB SYS 2

3 11715 CBM 092A 10F2 LEAKAGE MONITOR SYSTEM 2

20F2 CONTAINMENT VACUUM SYSTEM 2

1 11715 CBM 093A 10F3 REACTOR COOLANT SYSTEM LOOP 1 1

j 20F3 REACTOR COOLANT SYSTEM LOOP 2 1

l 30F3 REACTOR COOLANT SYSTEM Loop 3 1

1 11715 CBM 0938 10F3 REACTOR COOLANT SYSTEM 1

20F3 REACTOR C00LANT SYSTEM 2

11715 CBM 094A 10F2 RESIDUAL HEAT REMOVAL SYSTEM i

2 20F2 RESIDUAL MEAT REMOVAL SYSTEM 1

2 3

11715 CBM 095A 10F4 CHEMICAL AND VOLtME CONTROL SYSTEM 3

20F4 CHEMICAL AND VOLUME CONTROL SYSTEM 3

)

30F4 CHEMICAL AND VOLLME CONTROL SYSTEM 2

40F4 CHEMICAL AND VXLME CONTROL SYSTEM 2

11715 CBM 0958 10F2 CxfMICAL AND VOLUME CONTROL SYSTEM 2

3 20F2 CHEMICAL AND YCLLME CONTROL SYSTEM 2

vii Rev. O March 6, 1988

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NORTH AhhA t; NIT 1 ISI CLAS$1FICAi!CN BOUNDARY ORAWINGS

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CRAWING SHEET ORAWING CLASS CLASS CLASS NUMBER NUMBER TifLE 1

2 3

11715 CBM 095C 10F2 CHEMICAL AND VOLUME CONTROL SYSTEM 1

2 20F2 CHEMICAL Ak0 VOLUME CONTROL SfSTEM 1

2 11715 CBM 096A 1074 SAFEfY INJECTICN SYSTEM 2

20F3 SAFETY INJECTION SYSTEM 2

3 30F3 SAFELY INJECTION SYSTEM 2

3 11715 CBM 0968 10F4 SAFETY INJECT!CN SYSTEM 1

2 20F4 SAFETY INJECTICN SYSTEM 1

2 30F4 SAFETY INJECTION SYSTEM 1

2 40F4 SAFETY INJECTION SYSTEM 1

2 11715 CBM 098A 20F5 STEAM CEhERATOR 8LOWOOWN SYSTEM 2

l 30F5 STEAM CEhERATOR BLOWOOWN SYSTEM 2

40F5 STEAM CENER ATOR BLO@0WN SYSTEM 2

l 11715 CBM 107A 20F2 CHEMICAL FEED SYSTEMS 2

11715 CBM 1058 1CF2 SECONDARY PLANT CAS SUPPLY SYSTEM 3

l 11715 CBM 105C 10F1 MISCELLANEOUS GAS SUPPLY SYSTEM 2

11715 CBM 1068 10F4 CCHTAINMENT ATMOSPHERE CLEANUP SYS 2

20F4 CONTAINMENT ATMcSPHERE CLEANUP SYS 2

30F4 CONTAthMENT ATMOSPHERE CLEANUP SYS 2

40F4 CONTAINMENT ATMCSPHERE CLEANUP SYS 2

11715 CBM L&S 2 1071 LE E NDS & SYMBOLS 11715 F8 0400 1071 Alt CONo!TIONING CONDENSER WATER SYSTEMS 3

11715 FM 022J 10F1 SERV!CE WATER SYSTEM RESERV0!R SPRAY 3

11715 FM 022C 1071 SERVICE WATER SYSTEM RESERV0lt SPRAY 3

j l

11715 FM 078H 1071 SERVICE WATER SYSTEM 3

13075 C8M 093C 10f2 REACf04 C00LANT SYSTEM i

20F2 REACf04 COOLANT SYSTEM 1

i 13075 CSM 102C 10F1 CHEMICAL FEED SYSTEM 2

O viii Rev. O March 6,

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m VIRGINIA ELECTRIC AND-POWER COMPANY NORTH ANNA' POWER STATION UNIT 1 J.

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March 6, 1988' t

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1.0 INTRODUCTION

1.1 GENERAL INFORMATION North Anna Power Station Unit 1 is a Pressurized Water Reector located on Lake Anna in Louisa County, Virginia.

The plant employs a Westinghouse Electric Corporation Nuclear Steam Supply System.

The Inservice Inspection (ISI)

Program Plan for North Anna Power Station Unit 1 uas developed in compliance with the rules and regulations of 10CFR50.55a and Section XI of the ASME Boiler and Fressure Vessel Code, 1983 Edition with Addenda through the Summer 1983.

Where these rules ar3 determined to be impractical, specific relief is requested in writing.

The Inservice Inspection Program for Class 1, 2, and 3 Components and Component Supports is applicable for the ten year interval beginning June 6, 1988 and ending June 6,

1998.

This ten year interval will be the second inspection interval for North Anna Unit 1.

1.2 SYSTEM CLASSIFICATION

}

Forth Anna Power Static.. Unit 1, was issued construction permit No.

CPPR-77 in February 1971. The station design incorporates the codes and standards that were in effect when the equipment was purchased.

The codes and standards used for the design, fabrication, erection, and testing of safety-related components are commensurate with the importance of the safety functions to be performed.

The group classifications tabulated in the "Standard Format And Content of Safety Analysis Reports for Nuclear Power Reactors,"

issued in February 1971, and in Safety Guide No. 26, published in March 1972, incorporated, in most cases, later editions of codes than those in effect when the majority of safety-related equipment was designed.

Some of the equipment that would fall under a "group" as defined in Safety Guide No. 26 was designed to different codes or different editions of the same code.

For example, for different components that would be in the sane group, one may be designed to ASME III-1968, one to ASME III-1971, and one to ASME VIII-1968.

Therefore, pressure-containing components of safety-related systems do not fall under f.he group classification listed above.

Classification Boundary Drawings (CBDs) documenting the system classifications and defining the scope of the ISI Program, were developed to aid in the revieu and implementation of the subject prog m.

N1-001 Rev. 0 1-2

'c* arch 6, 1988

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' N1-002/68 2-1 Rev. 0

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r SECTION 2 s

TABLE OF CONTENTS v

s 2.0 INSERVICE INSPECTION PROGRAM FOR COMPONENTS PAGE 2.1 PROGRAM DESCRIPTION 2-3 2.1.1 Code Requirements 2-3' 2.1.2 Weld Selection for Class 1 Piping 2-3 2.1.3 Weld Selection for Class 2 Piping 2-3 2.1.4 Repairs and Replacements 2-3 2.2 PRCGRAM PLAN DESCRIPTION.

2-3 2.2.1 Inservice Inspection Program Plan Summary 2-3 2.2.2 Exemptions 2-4 2.2.3 Code Case Utilization 2-6 2.3 INSERVICE INSPECTION PLAN TABLE - CLASS 1 COMPONENTS 2-8 2.4 INSERVICE INSPECTION PLAN TABLE - CLASS 2 COMPONENTS 2-34 2.5 INSERVICE INSPECTION PLAN TABLE - CLASS 3 COMPONENTS 2-43 0

2.6 RELIEF REQUESTS 2-46 I

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~ N1-002/68 2-2 P.ev. O March 6, 1988 i

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2.0 INSERVICE INSPECTION PROGRAM FOR COMPONENTS r~N 2.1 PROGRAM DESCRIPTION 2.1.1 The Inservice Inspection Program ib Class 1,

2 and 3 components meets the requirements of Section XI of the ASME Boiler and Pressure Vessel %. 1983 Edition through the Summer 1983 Addendum.

Where c f.- c e

. requirements are determined to be impractical, specific requests for relief have been written and included in Section 2.6.

2.1.2 Weld selection for Class 1 piping will be su:h that 25% of the ISI Class 1 piping welds (circumferential, butt, $ ranch connections and socket welds) are examined during the second inspection-interval. Reexamination of welds examined during the first interval as required by Table IWB-2500-1, Extent and Frequency of Examinations, will be done as practicable providing the welds examined the first interval were evenly distributed across the pipe size, function and similar design.

2.1.3 Weld selection for Class 2 piping is determined by utilizing 10CFR50. 55a(b)(2)(iv)(A), and the selection criteria of ASME Sectfon XI, 1974 Edition through the Summer 1975 Addendum.

2.1.4 Repairs and replacements shall be in accordance with Station s

Administrative Procedures, which siall be in accordance with ASME Section XI, 1983 Edition through the Sur:mer 1983

Addendum, or later editions and addenda as may be incorporated by reference in 10CFR50.55a, and authorized for i

-use at North Anna Power Station in accordance with Station Technical Specification 6.8.

2.2 PROGRAM PLAN DESCRIPTION 2.2.1 The Inservice Inspection Program Plan Summary for the Component Program ia presented in Sections 2.3, 2.4 and 2.5 in a tabular format.

The con enents and associated v

requirements are listed in descending order according to Code Category and Item Numbers.

Those Categories and Item Numbers listed with "N/A" are for ccmponents not found at North Anna Unit 1 and are included for reference on ?./.

The following

)

information is included in the tables:

A.

Code Category The Section XI Examination Category as defined in Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1 for Class 1, 2 and 3 components, respectively.

B.

Item Nurber - The Section XI Item Number as listed in Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1.

All Item Numbers are listed for each Code Category with the exception of those associated with Program A of Category j

B-D.

C.

Part Examined TNe ASME Section XI description of the area to be examined.

N1-002/68 2-3 Rev. O March 6, 1988

O D.

Examination Method - Lists the_ examination method or Q

methods required by _the provisions of ASME Section XT..

The abbreviations used are as follows:

VOL - Volumetric per IWA-2230 SUR - Surface per IWA-2220 VIS - Visual per IWA-2211, 12, 13 and 14 (reference relief request CS-1 on page 3-17)

Li ts the It9mination E.

Alternate Examination Method 4

method that will be performed as an alternacive to the Code required examination as stated in a relief request.

F.

Examination Requirements / Figure Number Lists the applicable Section XI figure for determining the volume of the component to be examined.

Lists the applicable portion of G.

Acceptance Criteria Section XI for determining the acceptance criteria.

H.

Relief Roquest Number References a specific relief request contained in Section 2.6.

2.2.2 Specific implementation of the ISI Program for Class 1, 2 and n

F 3 components is detailed on the Classification Boundary Drawing Legends And Symbols Drawing (11715-CBM-L&S-2) and the coded ISI Classification Bourdary Drawings (CBDs).

2.2.2.1 ISI Class 1 Exemptions EX IWB-1220(a), Components that are connected to the reactor coolant system and part of the reactor coolant pressure boundary, and that are of such a sfze and shape so that upon postulated rupture the resulting flow of coolant from the reactor coolant systen under normal plant operating conditions is within the capacity of makeup systems which are operable from on-site emergency power (Components coded 1C per 11715-CBM-L&S-2).

EX IWB-1270(b)(1), Piping of 1 in. nominal pipe size and smaller, except for steam generator tubing (Components coded IB per 11715-CBM-L&S-2).

EX IWB-1220(b)(2) Components and their connections in piping of 1 in.

nominal pipe size and smaller (Components coded IB per 11715-CBM-L&S-2).

EX IWB-1220(c), Reactor Vessel head connections and O's/

associated piping, 2 in.

nominal pipe size and smaller, made inaccessible by control rod drive penetration, (Components coded ID per 11715-CBM-L&G-2).

N1-002/68 2-4 Rev. O March 6, 1988

2.2.2.2 ISI Class 2 Exemptions f,}

1 V

EX IWC-1220(a), Components of systems or portions of systems that during normal operating conditions are not required to operate or perform a system function but remain flooded under static conditions at a pressure of at least 80% of the pressure that the component or system will be subjected to when required to operate (Components coded 2E per 11715-CBM-L&S-2).

EX IWC-1220(b), Components of systems or portions of systems, other than Residual Heat Removal Systems and Emergency Core Cooling Systeme, that are not required to operate above a pressure of 275 psig or above a temperature of 200 *F (Components coded 2F per 11715-CBM-L&S-2).

EX IWC-1220(c), Component connections (including nozzles in vessels and pumps),

piping and associated

valves, and vessels and their attachments that are 4 in, nominal pipe size and smaller (Components coded 2B per 11715-CBM-L&S-2).

EX IWC-1230, Piping support members and piping support components that are encased in conc' ate.

OQ 2.2.2.3 ISI Class 3 Exemptions EX IWD-1220.1, Integral attachments of supports and restraints to components that are 4 in, nominal pipe size and smaller within the system boundaries of Examination Categories D-A, D-B, and D-C of Table IWD-2500-1 shall be exempt from the vi=>ual examination VT-3, except for Auxiliary Feedwater Systems (Components coded 3B and 3D per 11715-CBM-L&S-2)

(Auxiliary Feedwater Integral Attachments Examined-per Code 3E per 11715-CBM-L&S-2).

EX IWD-1220.2(a),

(b),

Integral attachments of

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supports and rest.raints to components exceeding 4 in, nomina) pipe size shall be exempt from the visual examination VT-3 provided the components are located in systems (or portions of systems) whose function is not required in support of reactor residual heat removal, containment heat

removal, and emergency core cooling and the components operate at a pressure of 275 psig or less and at a temperature of 200*F or less (See Note 4 of 11715-CBM-L&S-2).

O v

N1-002/68 2-5 Rev. O March 6, 1988

,-~s EX IWD-5223(e), open ended vent and drain lines from

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components extending beyond the last shutoff valve

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and open ended safety or relief valve discharge

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lines shall be exempt from hydrostatic testing.

2.2.3 The Inservice Inspection Program utilizes the following Code Cases either in part or whole as allowed by Regulatory-Guide 1.147 Revision 5:

2.2.3.1 CASE N-408 Alternate Rules For Exami..ation of Class 2 Piping Section XI, Division 1 The following exemption paragraphs have been utilized:

Paragraph (a)(6):

"piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal plant operating conditions."

Scope of Components exempted:

11715-CBM-091A Sheet 2 of 4 - 8" piping downstream of valves 1-QS-MOV-101A and 1-QS-MOV-101B to the spray header (8"-QS-37-153A-Q2, 8"-QS-39-153A-Q2, 8"-QS-22-153A-Q2 and 8"-QS-23-153A-Q2).

Note: The downstream pipe-to-valve-weld on 1-QS-MOV-101A and -101B will be subject to examination per IWC-1000.

11715-CBM-091A Sheet 3 of 4 Inside Recirculation Spray Pumps (1-RS-P-1A and 1-RS-P-1B),

10" pump discharge piping to coolers (10"-RS-1-153A-Q2 and 10"-RS-2-153A-Q2),

Recirculation Spray Coolers (1-RS-E-1A and 1-RS-E-1B), 10" cooler outlet piping (10"-RS-3-153A-Q2 and 10"-RS-4-153A-Q2),

and 8"

spray header piping (8"-QS-20-153A-Q2 and 8"-QS-21-153A-Q2).

11715-CBM-091A Sheet 4 of 4 - 10" piping downstream of 1-RS-MOV-156A and 1-RS-MOV-156B to coolers (10"-RS-9-153A-Q2 and 10"-RS-10-153A-Q2),

j Recirculation Spray Coolers (1-RS-E-1C and 1-RS-E-1D),

10" cooler discharge piping (10"-RS-11-153A-Q2 and 10"-RS-12-153 A-Q2) and 8"

spray header piping (8"-RS-22-153A-Q2, 8"-RS-23-153A-Q2, 8"-RS-17-153B, 8"-RS-18-153B, 8"-RS-32-153B, and 8"-RS-33-153B, to the blank flange).

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Note: The downstream pipe-to-valve weld on 1-RS-MOV-156A and -156B will be subject to examination per IWC-1000.

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N1-002/68 2-6 Rev. O March 6, 1988 l

2.2.3.2 CASE N-426 - Extent of VT-1 Examinations, Category B-G-2 of Table IWB 2500-1 Section XI, Division 1.

This code case has been utilized in its entirety.

N1-002/68 2-7 Rev. O March 6, 1988

O O

O 2.3 Class 1 omponents 2.3.1 Examination Category B-A, Pressure Retaining Welds in Reactor Vessel ALTERNATE EXAM RELIEF ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST' NO.

PARTS TO BE EXAMINED METHOD ME1 HOD FIG NO.

CRITERIA' (NDE-

)-

Bl.ll Reactor Vessel Circumferential Shell VOL IWB-2500-1 IWB-3510 Welds Bl.12 Reactor Vessel Longitudinal Shell VOL IWB-2500-2 IWC-3510

'j Welds j

.I Bl.21 Reactor Vessel Circumferential VOL IWB-2500-3 IWB-3510 l

W(ad Weld Bl.22 Reactor Vessel Meridional Head Weld VOL IWB-2500-3 IWB-3510 Bl.30 Reactor Vessel Shell-to-Flange

.VOL IWB-2500-4 IWB-3510 Weld Bl.40 Reactor Vessel Head-to-Flange Weld VOL & SUR SUR &

-IWB-2500-5 IWB-3510 1

PARTIAL VOL Bl.51 Reactor Vessel Beltline Region Repair VOL IWB-2500-1 IWB-3510 Welds and -2 N1-005b/68 2-8

.Rev. 0.

March 6, 1988 i

O O

O 2.3.2 Examination Category B-B, Pressure Retaining Welds in V.essels Other Than Resctor Vessels ALTERNATE EXAM RELIEF ITEM EXAM.

EXAFI REQUIRED /

ACCEPTANCE REQUEST-NO.

PARTS iO BE EXAMINED METI'0D METH0i)

FIG NO.

CRITERIA (NDE- )

B2.11 Pressurizer Circumferential VOL IWB-2500-1 IWB-3511 Shell-to-Head Welds B2,12 Pre:Jsurt er Longitudinal VOL IW3-2500-2 IWB-3511 Shell-co-Head Welds B2.21 Pressurizer Circumierential Head E/A N/A N/A j

Welds l

B2.22 Pressurizer Meridonial Head Helds N/A N/A N/A B2.31 Steam Generator CircumfeTential N/A N/A N/A Head Weids B2.32 Steam Generator Meridonial Head N/A N/A N/A welds B2.40 Steam Generator Tubesheet-to-Head VOL IWB-2500-6 IWB-3531 Weld N1-00Sb/68 2o Rev. 0 March.6, 1988

J 2.3.2 Examination Category B-B, Pressure Retaining Welds in Vessels Other Than Reactor Vessels'(con't.)

J ALTERNATE EXAM RELIEF l

ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST i

NO.

PARTS TO BE EXAMINED METHOD METHOD FIG NO.

CRITERIA (NDE- )

i i

)

i B2.51 Heat Enhange:-(Head) Circumferential N/A N/A N/A l

Head Welds i

B2.52 Heat Exchanger (Head) Meridenial N /..

N/A N/A Head Welds l

B2.60 Heat Exchanger (Shell)

N/A N/A N/A Tubesheet-to-Head Welds t

j B2.70 Heat Exchanger (Shell) Longitudinal N/A N/A N/A Welds i.

j B2.80 Heat Exchanger (Shell)

N/A N/A N/A l

Tubesheet-to-Shell Welds l

.i i

i 1

I I

4 I

i

.l 4

i 1

i f

N1-005b/68 2-19 Rev. 0 1

March 6, 1988 i

i~

2.3.3 Examination Category B-D, Full Prnetration Welds of Nozzles in Vessels Inspection Program B ALTERNATE EXAM RELIEF l

ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUESr NO.

PARTS TO BE EXAMINED METHOD METHOD FIG NO.

CRITERIA (NSE- )

I 1

B3.90 Reactor Vessel No7.zle-to-Vessel VOL IWB-2500-7 IWE-3512 Welds 1

)

B3.100 Reactor Vessel Nozzle Inside VOL IWB-2500-7 IWB-3512 Rasius Section i

B3.110 Pressurizer Nozzle-to-Vessel VOL PARTIAL VOL IWB-2500-7 IWB-3512 2

Welds 1

j B3.120 Pressurizer Nozzle Inside VOL VIS, VT-2 IWB-2500-7 IWB-3512 3

i Radias Section B3.130 Steam Generator Nozz1z-to-Vessel N/A N/A N/A 1

Weldo i

B3.140 Steam Generator Nozzle Inside VOL VIS, VT-1 IWB-2500-7 IWB-3512 3

j Radius Section 1

B3.150 Heat Exchanger Nozzle-to-Vessel N/A N/A h/A Uelds j

B3.169 Heat Exchanger Nozzle inside N/A N/A N/A i

Ra6fue Section I

l i

i i

i N1-005b/68 2-11 Rev. O j

March 6, 1988

-- ~. -

2.3.4 Examination ca.tegory B-E, Pressure Retaining Partial Penetration Welds In Vessels ALTERNATE EXAM RELIEF ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQdEST.

tiO.

PARTS TO BE EXVIINED METHOD METHOP FIC NO.

CRITERIA (NDE- )

w B4.11 Partial Penetration Vessel Nozzle.,

E4.12 Partial Penetrat$on Control Rod Drive Nozzles E4.13 Isrtial Penetration Instrumentaiica Nozzles B4.20 Ptessurizer Heater Penetration Welds t

J 4

I

NOTE: See Section 4.3.1 For Pressurae Testing Details j

1 i;

i i

i.

i i

I i

1 i

i l

1 i

N1-005b/68 2-12 Rev. 0 l

March 6, 1988 i

m,------.-_.-..--__.m_--.---,.--1--__----__

--ww-wW v

m-w w:

to s-

._._=.

l 2.3.5 Examination Category B-F, Pressure Retaining Dissimilar Metal Welds ALTERNATE EXAM RELIEF ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TU BE EXAMINED METHOD METHOD FIG NO..

CRITERIA (NDE-- )

l B5.10 Reactor Vessel Nominal Pipe Size VOL & SUR VOL IWB-2500-8 IWB-3514 6

2 4 in. Nozzle-to-Safe l

End Butt Welds B5.20 Reactor Vessel Nominal Pipe Size N/A N/A N/A l

< 4 in. Nozzle-to-Safe j

End Butt Welds B5.30 Reactor Vessel Nozzle-to-Safe N/A N/A N/A End Socket Welds B5.40 Pressurizer Nominal Pipe Size VOL & SUR SUR &

N/A N/A 4

2 4 in. Nozzle-to-Safe PARTIAL VOL End Butt Welds I

B5.50 Psessurizer Nominal Pipe Size N/A N/A N/A

~

< 4 in. Nozzle-to-Safe End Butt Welds B5.60 Pressurizer Nozzle-to-Safe N/A N/A

.N/A End Socket Welds l

i l

l I

N1-005b/68 2-13 Rev..O March 6, 1988

O O

C i

I 2.3.5 Examination Category B-F, Pressure Retaining Dissimilar Metal Welds (con't.)

i ALTERNATE EXAM RELIEF 1

i ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TO BE EXAMINED METHOD METHOD TIG NO.

CRITERIA (NDE- )

B5.70 Steam Generator Nominal Pipe VOL & SUR PARTIAL IWB-2500-8 IWB-3514 5

Size 2 4 in. Nozzle-to-Safe VOL & SUR l

End Butt Welds i

B5.80 Steam Generator Nominal Pipe N/A N/A N/A j

Size < 4 in. Nozzle-to-Safe j

End Butt Welds I

B5.90 Staan Generator Nozzle-to-Safe N/A N/A N/A i

End Socket Welds s

1 j

E5.100 Heat Exchanger Nominal Pipe N/A N/A N/A j

Size 2 4 in. Nozzle-to-Safe End Butt Welds i

l B5.110 Heat Fxchanger Nominal Pipe N/A N/A N/A j

Size < 4 in. Nozzle-to-Safe i

End Butt Welds l

d

,i l

i NI-005b/68 2-14 Rev. 0

}

March 6, 1988

J D

2.3.5 Examination Category B-F, Pressure Retaining Dissimilar Metal Welds (con.t)

ALTERNATE EXAM RELIEF j

ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TO BE EXAMINED METHOD METHOD FIG NO.

CRITERIA (NDE- )

i B5.120 Heat Exchanger Nozzle-to-Safe N/A N/A N/A l

End Socket Welds i

B5.130 Piping Nominal Pipe Size VOL & SUR IWB-2500-8 IWB-3514 2 4 in. Dissimilar Metal Butt Welds B5.140 Piping Nominal Pipe Size N/A N/A N/A i

< 4 in. Dissimilar Metal j

Butt Welds j

B5.150 Piping Dissimilar Metal N/A N/A N/A Socket Welds i

i I

1 i

I i

I l

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1 4

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4 4

N1-005b/68 2-15 Rev. O I

March 6, 1988 i

i O

O I

2.3.6 Examination Category B-C-1, Pressure Retaining Bolting, Greater Than 2 in. In Diameter j

ALTERNATE EXAM RELIEF j

ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST-NO.

PARTS TO BE EXAMINED METHOD METHOD FIC NO.

CRITERIA (NDE- )

i B6.10 Reactor Vessel Closure Head Nuts SUR B6.20 Reactor Vessel Closure Studs, VOL IWB-2500-12 IWB-3515

)

in Place l

B6.30 Reactor Vessel Closure Studs SUR & VOL IWB-2500-12 IWB-3515 j

when removed B6.40 Reactor Vessel Threads in Flange VOL IWB-2500-12 IWB-3515 B6.50 Reactor Vessel Closure Washers, VIS, VT-1 Surfaces i

Bushings i

l B6.60 Pressurizer Bolts and Studs N/A N/A N/A j

l B6.70 Pressurizer Flange Surface, N/A N/A N/A j

when connection disassembled l

B6.80 Pressurizer Nuts, Bushings, N/A N/A N/A i

and Washers-I j

B6.90 Steam Generator Bolts and Studs N/A N/A N/A 1

i i.

1 i

In course of preparation.

i 2

I.

1 N1-005b/68 2-16 Rev. 0 1

March 6, 1988 j

i 4

i

O O

O 2.3.6 Examination Category B-G-1, Pressure Retaining Bolting, Greater Than 2 in. In Diameter (con't.)

ALTERNATE EXAM RELIEF ITEM EXAM.

E~:AM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TO BE EXAMINED METHOD METHOD FIC NO.

CRITERIA (NDE- )

B6.100 Steam Generator Flange Surface, N/A N/A N/A when connection disassembled B6.110 Steam Generator Nuts, Bushings, N/A N/A N/A and Washers B6.120 Heat Exchanger Bolts and Studs N/A N/A N/A B6.130 Heat Exchanger Flange Surface, N/A N/A N/A B6.140 Heat Exchanger Nuts, Bushings.

N/A N/A N/A B6.150 Piping Bolts and Studs N/A N/A N/A B6.160 Piping Flange Surface, N/A N/A N/A when connection disassembled B6.170 Piping Nuts, Bushings, and Washers N/A N/A N/A N1-005b/68 2-17

.Rev. O March 6, 1988

O O

I 2.3.6 Examination Category B-C-1, Pressure Retaining Bolting, Creater Than 2 in. In Diameter (con't.)

ALTERNATE EXAM RELIEF ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TO BE EXAMINED METHOD METHOD FIG NO.

CRITERIA (NDE- )

i B6.180 Pumps Bolts and Studs VOL IWB-2500-12 IWB-3515 B6.190 Pumps Flange Surface,

'/IS, VT-1 Surfaces when connection disassembled B6.200 Pumps Nuts, Bushings, and Washers VIS, VT-1 Surfaces B6.210 Valves Bolts and Studs VOL VIS, VT-1 IWB-2500-12 IWB-3515 7

0 j

B6.220 Valves Flange Surface, VIS, VT-1 Surfaces when connection disassembled B6.230 valves Nuts, Bushings, and Washers VIS, VT-1 Surfaces i

In course of preparation.

N1-005b/68 2-18 Rev. O March 6, 1988:

m..

l

- 2.3.7 Examination Category B-G-2, Pressure Retaining Bolting, 2 in. and Less In Diameter I

ALTERNATE EXAM RELIEF ITEM EXAM.

EXAM REQUIRED /-

ACCEPTANCE REQUEST NO.

PARTS TO FE EXAMINED METHOD METHOD FIG NO.

CRITERIA (NDE- )

B7.10 Reactor Vessel Bolt % Studs and Nuts VIS, VT-1 Surface B7.20 Pressurizer Bolts, Studs, and Nuts VIS, VT-1 Surface B7.30 Steam Generator Bolts Studs, VIS, VT-1 Surface and Nut.

B7.40 Heat Exchanger Bolts, Studs and Nuts N/A N/A N/A b

I B7.50 Piping Bolts, Studs, and Nuts VIS, VT-1 Surface B7.60 Pumps Bolts, Studs, and Nuts VIS, VT-I Surfar.

B7.70 Valves Bolts, Studs. and Nuts VIS, VT-1 Surface B7.80 CRD Housings Bolts, Studs and Nuts VI'i, VT-1 Surface l

l i

l l

l

In course of preparation.

l N1-005b/68 2-19 Rev. O March 6,.1988

. ~.

i O

2.3.8 Examination Category B-H, Integral Attachments for Vessels l

l l

ALTERNATE EXAM RELIEF i

ITEM EXAM.

EXAM REQUIkED/

ACC:*TANCE REQUEST l

NO.

PARTS TO BE EXAMINED METHOD MET 110D FIG NO.

Cf.ITERIA (NDE- )

1 1

l B8.10 Ret.ctor W ssel Integrally Welded N/A N/A N/A Attachments B8.20 Pressurizer Integrally Welded VOL OR SUR IWB-2500-13 IWB-3516 l

Attachments

-14, and -15 B8.30 Stea.m Generator Integrally Welded N/A N/A N/A i

Attachments i

B8.40 Heat Exchanger Inier,rall,* Welded N/A N/A N/A t

j Attachments i

i l

t 1

l i

i i

i

}

N1-005b/68 2-20 Rev. O j

March 6, 1988 4.

<m..

O O

O 2.3.9 Examination Category B-J, Pressure Retaining Welds in Piping ALTERNATE EXAM RELIEF ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TO BE EXAMINED METHOD METHOD FIC NO.

CRITERIA (NDE- )

B9.11 Nominal Pipe Size 2 4 in.

VOL & SUR SUR &

IWB-2500-8 IWB-3514 8

l Circurferential Welda PARTIAL VOL 4

B9.12 Nominal Pipe Size 2 4 in.

VOL & SUR IWB-2500-8 IWB-3514 Longitudinal Welds B9.21 Nominal Pipe Size < 4 in.

SUR IWB-2500-8 IWB-3514 Circumferential Welds B9.22 Nominal Pipe Size < 4 in.

SUR IWB-2500-8 IWB-3511 Longitudinal Welds B9.31 Nominal Pipe Size 2 4 in.

VOL & SUR SUR &

IWB-2500-9, IWB-3514 9

Branch Pipe Connection Welds PARTIAL VOL

-10, and -11 B9.32 Nominal Pipe Size < 4 in.

SUR IWB-2500-9, IWB-3514 Branch Pipe Connection Welds

-10, and -11 B9.40 Socket Welds SUR IWB-2500-8 IWB-3514 N1-005b/68 2-21 Rev. O March 6, 1988

'l O

O O

2.3.10 Examination Category B-K-1, Integral Attachments for Piping, Pumps, and Valves ALTERNATE EXAM RELIEF ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TO BE EXAMINED METHOD METHOD FIC NO.

CRITERIA (NDE- )

B10.10 Piping Integrally Welded VOL or SUR IWB-2500-13 IWB-3516 Attachments

-14, and -15 B10.20 Pumps Integrally Wolded VOL or SUR IWB-2500-13, 1WB-3516 Attachments

-14, and -15 B10.30 Valves Integrally Welded VOL or SUR IWB-2500-13, IWB-3516 Attachments

-14, and -15 l

l t

P F

I L

i N1-005b/68 2-22 Rev. O March 6, 1988-

1 i

i 2.3.11 Examination Category B-L-1, Pressure Retaining Welds in Pump Casings l

ALTERNATE EXAH RELIEF j

ITEM EXAM.

EXAM REQUIRED /-

ACCEPTANCE REQUEST.

i NO.

PAR"'S TO BE EXAMINED METHOD METHOD FIG NO.

CRITERIA (NDE- )

1 4

1 j

B12.10 Pump Casing Welds VOL SUR IWB-2500-16 IWB-3518 10 i

i i

l 1

l l

I i

1 4

l

?

I i

l 1

i, I

I N1-005b/68 2-23 Rev. O j

March 6, 1988 i-. _ _. - _ _ _ _ _ _.-_ _, - _ _ _ _ _ _.

ll1 8

8.

9.

1

)

T 6

FS 0

O EE -

1 I UE

.hc O

LQD vr EEN ea RR(

RM ECNA AI TR PE ET CI CR M

AC M

/

D l s E.

ae RO nc I N ra MU ef AQG t r XEI nu P-ERF I S E

1 T

A T

N D

V R

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EMI TAT S

LXE I

AEM V

4 2

2 3

O

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V s

0 g

Mi n

AT S

i XE I

s EM V

a C

p mu P

2

-L

-B yrog e

t D

a E

C N

I n

M n

o A

o i

X i

t E

t a

a n

E g

r i

B n

a m

i p

a O

s e

x T

a r

E C

p ST p

f 2

R m

o 1

A u

P P

e 3

s 8

r 6

2 u

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0 c

5 M

2 0

n 0

E.

2 I

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2.3.13 Examination Category B-M-1, Pressure Retaining Welds in Valve Bodies

~

ALTERNATE EXAM RELIEF ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS To *F EXAMINED METHOD METHOD FIC NO.

CRITERIA (NDE- )

B12.30 Valves, Nominal P;pe Size N/A N/A N/A l

< 4 in. Valve Body Welds B12.40 Valves, Nominal Pipe Size N/A N/A N/A 2 4 in. Valve Body Welds I

l t

I l

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n 1

1 N1-005b/68 2-25.

Rev.-0 March 6,~1988-

O O

O 1

2.3.14 Examination Category B-M-2, Valve Bodies l

l i

ALTERNATE EXAM RELIEF.

ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TO BE EXAMINED METHOD METHOD FIG NO.

CRITERIA (NDE- )

B12.50 Valve Body, Exceeding.4 in.

VIS, VT-3 VIS, VT-3.

Internal

'll Nominal Pipe Size Surfaces

In course of preparation.

NI-005b/68 2-26 Rev. 0-March 6, 1988

-_._ _ -.=___ _..

m.

l f

l 2.3. 5 Examination Category B-N-1, Interior of Reactor Vessel I

i.

1 l

ALTERNATE EXAM RELIEF i

ITEM EXAM.

EXAM REQUIREb/

ACCEPTANCE-REQUEST' NO.

PARTS TO BE EXAMINED METHOD METHOD FIG NO.

CRITERIA (NDE - )

j l

B13.10 Reactor Vessel Vessel Interior VIS, VT-3 Accessible j

areas 1

i I

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l

)

4 i

j

In course of preparation.

~

4 1

I 2

Rev. O N1-005b/68 2-27 f

March 6, 1988 L

i O

I 1

2.3.16 Examination Category B-N-2, Integrally Welded Core Support Structures and Interior Attachments to Reactor Vessels ALTERNATE EXAM RELIEF ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TO BE EXAMINED METHOD METHOD FIC NO.

CRITERIA (NDE- )

1 B13.20 BWR's Only N/A N/A N/A B13.30 BWR's Only N/A N/A N/A I

B13.50 Reactor Vessel Interior Attachments VIS, VT-!

Accessible Within Beltline Region welds i

B13.60 Reactor Vessel Interior Attachments VIS, VT-3 Accessible j

Beyond Beltline Region welds i

4 s

I i

1 4

i I

i a

I t

l 1

l I

i i

In course of preparation.

i i

l l

l i

N1-00Sb/68 2-28 Rev. 0 j

March 6, 1988-

1 I

1 j

2.3.17 Examination Category B-N-3, Removable Core Support Structures I

i l

ALTERNATE EXAM RELEIF 4

ITEM EXAM.

EXAM REQUIRED /.

ACCEPTANCE REQUEST j

NO.

PARTS TO BE EXAMINED METHOD METHOD FIG NO.

CRITERIA (NDE- )

1 e

k i

B13.40 BWR's Only N/A N/A N/A 4

{

l B13.70 Reactor Vessel Core Support VIS, VT-3 Accessible j

Structure Surfaces 1

]

I 4

i i

i 2

i i

1 i

c.

a k

In course of preparation.

I l'

1 i

j l

N1-005b/68 2-29 Rev. 0 March 6, 1983 t

i*-

p__-

I 1

l i

i i

I

{

2.3.18 EFamination Category B-0, Pressure Retaining Welds in Control Rod Housings l

l ALTERNATE EXAM RELIEF ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TO BE EXAMINED METHOD METTIOD FIG NO.

~ CRITERIA (NDE- )

B14.10 Reactor Vessel Welds in CRD Housing VOL or SUR IWB-2500-18 IWB-3523 i

)

i l

I 1

i 1

l l

1-t l

I r

9 1

)

i 4

1 4

1 N1-005b/68 2-30

'Rev. 0 j

' March 6, 1988 d

O O

2.3.19 Examination Category B-P, All Pressure Retaining Components ALTERNATE EXAM RELIEF ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TO BE EXAMINED METHOD ME1 HOD FIC NO.

CRITERIA (NDE- )

B15.10 Reactor Vessel Pressure Retaining Boundary j

B15.11 Reactor Vessel Pressure Retaining i

Boundary B15.20 Pressurizer Pressure Retaining Boundary B15.21 Pressurizer Pressure Retaining Boundary 4

B15.30 Steam Generator Pressure Retaining i

Boundary i

B15.31 Steam Generator Pressure Retaining Boundary j

B15.40 Heat Exchanger Pressure Retaining N/A N/A N/A i

Boundary B15.41 Heat Exchanger Pressure Retaining N/A N/A N/A I

Boundary 1

l 1

I

NOTE: See Section 4.3.1 For Pressure Testing Details i

N1-005b/68 2-31 Rev. 0 March 6, 1988

t 2.3.19 Examination Category B-P, All Pressure Retaining Components (con't.)

ALTERNATE EXAM RELIEF ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TO BE EXAMINED METHOD METHOD FIG NO.

CRITERIA (NDE- )

B15.50 Piping Pressure Retaining Boundary 1

B15.51 Piping Pressure Retaining Boundary l

1 B15.60 Pumps Pressure Retaining Boundary 4

B15.61 Pumps Pressure Retaining Boundary B15.70 Valves Pressure Retaining Boundary p,

B15.71 Valves Pressure Retaining Boundary I

J

NOTE: See Section 4.3.1 For Pressure Testing Details I

I i

l 7

1 i

4 N1-005b/68 2-32 Rev. 0

i l

2.3.20 Examination Category B-Q, Steam Generator Tubing l

ALTERNATE EXAM RELIEF.

l ITEM EXAM.

EXAM REQUIRED /

ACCEPTANCE REQUEST A I NO.

PARTS TO BE EXAMINED METHOD METHOD FIC NO.

CRITERIA (NDE- )

B16.10 Steam Generator Tubing in Straight N/A N/A N/A Tube Design t

4

]

B16.20 Steam Generator Tubing in U-Tube VOL NONE

' Hot Leg.

IWB-3521 12 M;

i, Design and U-Bend t

1 i

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1 i

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r i

j i

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1

-Q.

.[

- }

N1.-005b/68 2-33 Rev. 0 March 6, 1988

i 2.4 Class 2 Components i

l 2.4.1 Examination Category C-A, Pressure Retaining Welds in Pressure Vessels ALTERNATE EXAM RELIEF j

ITEM EXAM EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TO BE EXAMINED METHOD METHOD FIG NO.

CRITERIA (NDE- )

i i

~

.t C1.10 Pressure Vessel VOL PARTIAL' IWC-2500-1 IWC-3000 13,14,15 Circumferential VOL 16,17,18 Shell Welds l

I 1

C1.20 Pressure Vessel VOL IWC-2500-1 IWC-3000 Circumferential Head Welds i

C1.30 Pressure Vessel VOL PARTIAL IWC-2500-2 IWC-3000 16

}

Tubesheet-to-Shell VOL i.

Weld i

i

,I h

I i

i I

j N1-005c/68 2-34 Rev. O March 6, 1988 I

l 1

4 2.4.2 Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels ALTERNATE EXAM RELIEF ITEM EXAM EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TO BE EXAMINED METHOD METHOD FIC NO.

CRITERIA (NDE-

)-

C2.11 Pressure Vessel SUR IWC-2500-3 IWC-3000 s 1/2 in.

)

Nominal Thickness 4,

Nozzle-to-Shell l

(or Head) Weld

]

1 C2.21 Pressure Vessel SUR &

SUR &

IWC-2500-4(a) IWC-3000 19

> 1/2 in.

VOL PARTIAL VOL or (b) j Nominal Thickness Nozzle-to-Shell i

)

(or Head) Weld 1

without Reinforcing i

Plate f

C2.22 Pressure Vessel VOL VIS, VT-1 IWC-2500-4(a) IWC-3000 3

> 1/2 in. Nominal or (b) 1 Thickness j

Nozzle Inside

}

Radius Section without Reinforcing Plate C2.31 Pressure Vessel SUR IWC-2500-4(c) 1WC-3000

> 1/2 in.

Nominal Thickness j

Reinforcing Plate Welds j

to Nozzle and Vessel 1

i i

i 1

N1-005c/68 2-35 Rev. 0 March 6, 1988' t.

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2.4.2 Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels (con.t)

ALTERNtaTE EXAM RELIEF

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ITEM EXAM EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TO BE EXAMINED METHOD METHOD FIG NO.

CRITERIA (NDE- )

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C2.32 Pressure Vessel VOL IWC-2500-4(c) IWC-3000

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> 1/2 in.

Nominal Thickness i

Nozzle-to-Shell (or Head) Welds j

When inside of l

Vessel is Accessible C2,33 Pressure Vessel VIS, VT-2 N/A No leakage t

> 1/2 in.

i Nominal Thickness Nozzle-to-Shell i

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(or Head) When j

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J N1-005c/68 2-36 Rev. 0.

March 6, 1988..

l 2.4.3 Examination Categor'f C-C, Integral Attachments For Vessels, Piping, Pumps, and Valves ALTERNATE EXAM RELIEF' ITEM EXAM EXAM REQUIRED /

ACCEPTANCE REQUEST NO.

PARTS TO BE EXAMINED METHOD METHOD FIG NO.

CRITERIA (NDE- )

C3.10 Pressure Vessel SUR IWC-2500-5 IWC-3000 Integrally Welded Attachments l

C3.20 Piping SUR IWC-2500-5 IWC-3000 Integrally Welded I

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Attachments C3.30 Pump SUR IWC-2500-5 IWC-3000

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Integrally Welded l

Attachments I

C3.40 Valve SUR IWC-2500-5 IWC-3000 Integrally Welded l

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i N1-005c/68 2-37 Rev. 0 1

March 6, 1988

1/2 in.

l Circumferential

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Piping Welds 1

C5.22 Nominal Wall SUR &
SUR &
IWC-2500-7 IWC-3000
'20 I
Thickness VOL PARTIAL VOL
> 1/2 in.
Longitudinal Piping Welds i
C5.31 Nominal Branch Pipe SUR IWC-2500-9,to IWC-3000 21 l
Size > 4 in.
-13, inclusive Circumferential Weld j
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i N1-005c/68 2-39 Rev. O j
March 6,'1988 H
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O 2.4.5 Examination Category C-F, Pressure Retaining Welds In Piping (con't.)
LTERNATE EXAM RELIEF ITEM EXAH ZXAM REQUIRED /
ACCEPTANCE REQUEST NO.
PARTS TO BE EXAMINED METIIOD MET 110D FIC NO.
CRITERIA (NDE- )
C5.32 Nominal Branch Pipe Size SUR IWC-2500-12, IWC-3000
> 4 in. Longitudinal Weld and -13 i
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N1-005c/68 2-40 March 6, 1988 a
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2.4.6 Examination Category C-C, Pressure Retaining Welds In Pumps And Valves a
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ALTERNATE EXAM RELIEF ITEM EXAM EXAM REQUIRED /
ACCEPTANCE REQUEST i
NO.
PARTS TO BE EXAMINED METHOD METHOD FIC NO.
CRITERIA (NDE- )
j i
a C6.10 Pump SUR IWC-2500-8 IWC-3000 22,23 r
Pump Casing i
Welds I
C6.20 Valve Body Welds N/A N/A N/A l
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l N1-005c/68 2-41 Rev.'. 0.
March 6, 1988
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2.4.7 Examination Category C-H, All Pressure Retaining Components ALTERNATE RELIEF ITEM EXAM
- EXAM TEST ACCEPTANCE REQUEST NO.
PARTS TO BE EXAMINED METHOD METHOD REQUIRED CRITERIA (NDE- )
1 C7.10 Pressure Vessel Pressure Retaining Components C7.20 Pressure Vessel Pressure Retaining Components C7.30 Piping
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Pressure Retaining Components
)
f C7.40 Piping j
Pressure Retaining j
Components C7.50 Pump Pressure Retaining r
l Components a
j C7.60 Pump Pressure Retaining Components C7.70 Valve Pressure Retaining Components f
C7.80 Valve j
Pressure Retaileg Components i
NOTE: See Section 4.3.2 For Pressure Testing Details i
N1-005c/68 2-42 Rev. O l
March 6, 1988
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2.5 Class 3 Components i
2.5.1 Examination Category D-A, Systems In Support of Reactor Shutdown Function
.t ALTERNATE TEST RELIEF ITEM EXAM EXAM AND EXAM ACCEPTANCE REQUEST i
NO.
PARTS TO BE EXAMINED METHOD METHOD REQUIREMENTS CRITERIA (NDE- )
}
D1.10 Pressure Retaining Components D1.20 Integral Attachment-VIS, VT-3 IWD-2500-1 IWD-3000
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Component Supports and
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Restraints D1.30 Integral Attachment-VIS, VT-3 I h 2500-1 IWD-3000 l
Mechanical and Hydraulic j
Snubbers 1,
D1.40 Integral Attachment-VIS, VT-3 IWD-2500-1 IWD-3000 l
Spring Type Supports 1
j DI.50 Integral Attachment-VIS, VT-3 I h 2500-1 IWD-3000 Constant Load Type Supports I
l D1.60 Integral Attachment-VIS, VT-3 IWD-2500-1 IWD-3000 Shock Absorbers l
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NOTE: See Section 4.3.3 For Pressure Testing Details 3
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i N1-005d/68 2-43 Rev. O j
March 6, 1988' t
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1 2.5.2 Examination Category D-B, Systems In Support of Emergency Core Cooling, Containment Heat' Removal, Atmosphere Cleanup, and Reactor Residual Heat Removal i
j ALTERNATE TEST-RELIEF l
ITEM EXAM EXAM AND EXAM ACCEPTANCE REQUEST NO.
PARTS TO BE EXAMINED METHOD METHOD REQUIREMENTS.
CRITERIA (NDE- )
I D2.10 Pressore Retaining Components D2.20 Integral Attachment-VIS, VT-3 IWD-2500-1 IWD-3000 Component Supports and Restraints j
D2.30 Integral Attachment-VIS, VT-3 IWC-2500-1 IWD-3000 i
Mechanical and Hydraulic j
Snubbers D2.40 Integral Attachment-VIS, VT-3 IWD-2500-1 IWC-3000 l
Spring Type Supports D2.50 Integral Attachment-VIS, VT-3 IWD-2500 IWD-3000 Constant Load Type Supports f
D2.60 Integral Attachment-VIS, VT-3 IWD-2500-1
'IWD-3000 l
Shock Absorbers 1
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NOTE: See Section 4.3.3 For Pressure Testing Details 1,
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1 N1-005d/68 2-44 Rev. 0
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. March 6 1988 4
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2.5.3 Examination Category D-C, Systems In Support of Residual Heat Removal From Spent Fuel Storage Pool ALTERNATE TEST RELIEF ITEM EXAM EXAM AhD. EXAM ACCEPTANCE REQUEST NO.
PARTS TO BE EXAMINED METHOD METEOD REQUIREMENTS CRITERIA (NDE- )
D3.10 Pressure Retaining Components D3.20 Integral Attachment-VIS, VT-3 IWD-2500-1 IWD-3000 Component Supports and Restraints D3.30 Integral Attachment-VIS, VT-3 IWD-2500-1 IWD-3000 Mechanical and Hydraulic Snubbers D3.40 Integral Attachment-VIS, VT-3 IWD-2500-1 IWD-3000 Spring *, pe Supports D3.50 Integral Attachment-VIS, VT-3 IWD-2500-1 IWD-3000 Constant Load Type Supports D3.60 Integral Attachment-VIS, VT-3 IWD-2500-1 IWD-3000 Shock Absorbers
NOTE: See Section 4.3.3 For Pressure Testing Details s
N1-005d/68 2-45 Rev. O
_ March 6, 1988
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l 2.6 Inservice Inspection Program Relief Requests The following relief requests identify those ASME Section XI Code requirements considered _ to be impractical.
The basis for the relief j
request and the alternate testing to be performed is given.
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N1-002/68 2-6 Rev. O March 6. 1988
t RELIEF REQUEST NDE-1 s
(V I.
IDENTIFICATION OF COMPONENTS Reactor Vessel (1-RC-R-1): Head-To-Flange Weld II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum, requires the Category B-A reactor vessel head-to-flange veld have a surface and a volumetric examination each inspection interval in accordance with subsection IVB-2500.
A full volumetric es; amination is not practicable.
III. BASIS FOR RELIEF The geometric configuration of the reactor vescel head-to-flange veld limits the extent to which ultrasonic examinations can be performed from the flange side of the veld.
IV.
ALTERNATE EXAMINATION The surface examination util be performed in accordance with the Code requirements and a volumetric examination will be perfctmed to the extent practicable.
V 4
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N1-002/68 2-*7 Rev. O March 6, 1988
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RELIEF REQUEST NDE-2 l
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I.
IDENTIFICATION OF COMPONENTS Pressurizer (1-RC-E-2): Nozzle-To-Vessel Welds II.
IMPRACTICAL CODE REQUIREMENTS f
i Section XI of the 'ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summor 1983 Addendum, requires the pressurizer nozzle-to-vessel welds of Category B-D be examined volumetrically each inspection interval in accordance with subsa.ction IVB-2500.
A full volumetric examination is not practicable.
III. BASIS FOR RELIEF The pressurizer has six category B-D nozzle-to-vessal welds. The geometric configuration of the nozzle prevents ultrasonic examinations from being performed from the nozzle itself.
Examinations must be performed from the vessel head and since the 1
vessel interior is cladded, onl/ a IT examination can be performed j
effectively.
Geometric _ constraints and physical limitetions restrict access to the nozzle bore which would be necessary to perform other examination techniques.
IV.
ALTERNATE EXAMINATION An ultrasonic examination will be performed to the extent j
practicable.
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i N1-002/68 2-48 Rev. O March 6, 1988 i
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RELIEF REQUEd f hTE-3 O()
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IDENTIFICATION OF COMPONENTS Pressurizer (1-RC-E-2) and Steam Generators (1-RC-E-1 A,1-RC-E-1B and 1-RC-E-1C): Nozzle Inside Radius Sections II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum, requires the nozzle inside radius section of Category B-D and Category C-B nozzles on the pressurizer and steam generators must be examined volumetrically in accordance with subsections IWB-2500 and IWC-2500 during each inspection interval. Categories B-D and C-B include nozzles with full penetration welds to the vessel shell (or head) and integrally cast nozzles, but exclude manways and handholes either welded to or integrally cast in the vessel.
Relief is requested from the volumetric examination requirements of the nozzle inner radii for the steam generator and pressurizer nozzles.
III. BASIS FOR RELIEF Relief from examining the Code required volume is requested based upon the follouing criteria:
1) Nozzles in the pressurizer and steam generators contain inherent geometric constraints and clad inner surfaces which limit the ability to perform meaningful volumetric (UT) examinations of the inner radii areas. The pressurizer surge line noazie I.D. is physically restricted by the sparger, the thermal sleeve, and heater bank interferences.
The steam generator main steam oozzles are physically restricted by the flow limiting devices.
2) Presently, there is no comprehensive examination techrique, nor guidance for such in the ASME Code, which would provide a conclusive assessment for the Code required volumetric examinations of these inner radii, particularly since no preservice results are available for review.
3) Radiography (RT) is not a viable examination technique due to the same inherent geometric constraints and accessibility limitations that restrict the effectiveness of the ultrasonic examination method.
In addition, high radiation levels on primary system nozzles would expose radiographic film, causing it
'7q" beyond acceptable standards.
N1-002/68 2-49 Rev. O March 6, 1988 i
I L
IV.
ALTERNATE EXAMINATION j_
1)
The six Category B-D pressurizer nozzle inside radius i
sections shall be visually examined (VT-2) from the 0.
D.
every refueling outage, aftsr the unit has reached normal operating pressure and temperature.
2)
The three Category B-D primary inlet and_three Category B-D outlet nozzle inside radius sections on the steam generators i
I will be visually examined (VT-1) from the I.D.
using direct 4
or remote techniques at the frequency specified in Table IWB-2412-1.
3)
The three Category C-8 steam generator feedwater nozzle thermal sleeves restrict access to the nozzle inside radius section. A visual examination (VT-1) of the accessible areas of the nozzles inside radius section will be performed at the i
frequency specified in Table IWC-2412-1 to the extent practicable.
l 4)
The three Category C-B steam generator main steam nozzle flow limiting devices restrict access to the nozzle inside radius l
section.
A visual examination (VT-2) of the 0. D, will be l
performed when the unit has reached normal operating pressure j
and temperature at the frequency specified in the Table IWC-2412-1.
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l Rev. O N1-002/68 2-50 March 6, 1988 i
RELIEF REQUEST NDE-4 (3
I.
IDENTIFICATION OF COMPONENTS Pressurizer (1-RC-E-2): Nozzle-To-Safe End Welds II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum, requires the Category B-F pressurizer nozzle-to-safe end welds have a surface and volumetric examination each inspection interval in accordance with subsection IWB-2500.
A full volumetric examination is not practicable.
I' -
. SIS FOA RELIEF Etamination of the pressurizer nozzle-to-safe end welds is limited by the geometry and surface condition of the nozzle. The physical geometry of the nozzle-to-safe end weld permits ultrasonic examination of only the weld and the pipe side of the weld.
IV.
ALTERNATE EXAMINATION The surf ace examinatic' n; be t e formed in accordance with the Code requirements and lumetric examination will se performed on the veld and the base metal on the pipe side of the weld to the extent practicable.
C)
N1-002/68 2-51 Rev. O Msrch 6, 1988
RELIEF REQUEST NDE-5 (vD I.
IDENTIFICATION OF COMPONENTS Steam Generators (1-RC-E-1A,-
1-RC-E-1B, and 1-RC-E-1C):
Nozzle-To-Safe End Welds and Pipe-To-Safe End Welds II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure. Vessel Code, 1983 Edition through the Summer 1983 Addendum, requires the Category B-F steam generator nozzle-to-safe end welds'and pipe-to-safe end welds have a surface and volumetric examination each inspection interval in accordance with subsection IWB-2500.
A full volumetric examit tion is not practicable.
III. BASIS FOR RELIEF Examination of the steam generator nozzle-to-safe. end welds and pipe-to-safe end welds is limited by the geometry cJ surface condition of the nozzle.
Since the nozzle side is in the rough as-cast condition and because of the nozzle material characteristics, ultrasonic examination is 1 aited to the weld and the pipe side of the weld.
IV.
ALTERNATE EXAMINATION b\\
\\j An angle beam and calibrated zero degree volumetric examination on the weld and the base metal on the pipe side of the weld will be performed to"the extent practicable. A surface examination will be performed on
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the weld and the base metal on the pipe side of the weld.
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N1-002/68 2-52 Rev. O March 6, 1988
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RELIEF REQUEST NDE-6 pO I.
IDENTIFICATION OF COMPONENTS Reactor Vessel (1-RC-R-1):
Nozzle-To-Safe End Welds II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Adlendum, specifies in Table IWB-2500-1 (Category B-F, Item Number B5.10) that a volumetric and a surface examination of the'outside diameter (OD) on the reactor vessel nozzle-to-safe end welds be performed.
III. BASIS FOR RELIEF The OD surface examination would require a significant amount of time-for the removal of interference and shielding materials, surface preparation, and examination.
High radiation exposures would be expected should this examination be performed.
Improved i
technology and advancements in the area of ultrasonic examination have eliminated the need to examine these welds from the OD.
IV.
ALTERNATE EXAMINATION Alternately, it is requested that a full volumetric' examination from the inside diameter (ID) be accepted in lieu of the surface i
f--)s e,
and volumetric examinations from the OD.
A full volumetric examination from the ID of a Surry calibration block has demonstrated sensitivity adequate to resolve a 5% r.otch on the OD.
Additionally, a flaw, which is an estimated eighty percent of the critical flaw as described in ASME Section XI IWB-3000 Acceptance Standards for Flaw Indications, has been induced into a mock-up block.
This flaw has been satisfactorily detected and distinguished from the bimetallic interf ace.
Demonstration of both capabilities at the Westinghouse Waltz Mill Calibration Facility have been found acceptable by the Authorized Nuclear Inservice Inspector as an examination method equivalent to those performed from the OD.
O N1-002/68 2-53 Rev. O March 6, 1988
RELIEF REQUEST NDE-7 r3 I.
IDENTIFICATION OF COMPONENTS s.
Reactor Coolant Pump Loop Stop Valves:
(1-RC-Mov-1590, 1-RC-MOV-1591, 1-RC-MOV-1592, 1-RC-MOV-1593,- 1-RC-MOV-1594, and 1-RC-MOV-1595) _ Class 1 Valve bolting greater than two inches in diameter II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum, requires valve bolts and studs greater than two inches in diameter of Category B-G-1 to be examined volumetrically in accordance with subsection IWB-2500 during each inspection inte rval.
A meaningful volumetric examination of the Loop Stop Valve Studs is not practicable.
III. BASIS FOR RELIEF The studs (24 studs per valve) used in the reactor coolant loop stop valves are ASME SA-540 Grade B24 with a hex head and a 3/4 in, heater hole drilled completely through the stud. The valve body is ASME SA-351 Grade CF8M material.
Due to the material characteristics of both the studs and the valve body, removal may cause significant damage to both the studs and the valve body.
/
In place ultrasonic examination from the top surface of the studs
( ))
provides little meaningful data due to the length (18 inches) and geometric configuration of the stud.
Ultrasonic examination techniques from the I.
D.
of the stud using a bore-hole probe require a significant amount of examination time.
It is estimated that it will take approximately 30 to 45 minutes to examine each stud using the bore-hole probe. Radiation readings in the general area are estimated to be 100 mr/ hour. Contact readings on the valve are estimated to be between 700 and 800 mr/ hour. Performing the examination from the bore could result in e total of 14.4 man rem exposure per valve.
IV.
ALTERNATE EXAMINATION A visual examination of the bolting will be performed in place under tension as rectired by Category B-G-2.
NOTE: The cylindrically guided wave technique is currently being evaluated by Virginia Electric and Power Company.
This relief request will be revised, if necessary, upon completion of our evaluation.
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N1-002/68 2-54 Rev. O March 6, 1988
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RELIEF REQUEST NDE-8 I.
IDENTIFICATION OF COMPONENTS Class 1 Circumferential piping welds four inches nominal pipe size and greater II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and-Pressure Vessel Code, 1983
. Edition through the Summer 1983 Addendum, requires circumferential welds in piping 'four inches nominal pipe size and greater of Category B-J be examined volumetrically and by surface examination in accordance.with subsection IWB-2500 during each inspection interval. A full volumetric examination may not be practicable, III. BASIS FOR RELIEF Limitations from full volumetric examination may occur due to geometric discontinuities such as pipe to nozzle welds, pipe to fitting welds, branch connections or supports in the examination area.
Full volumetric examination of a weld would be dependent upon the geometric configuration.
IV.
ALTERNATE EXAMINATION g-The surface examination vill be performed in accordance with-Code
(
requirements.
An ultrasonic examination will be.' performed to the extent practicable.
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N1-002/68 2-55 Rev. O March 6, 1988 j
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RELIEF REQUEST NDE-9
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I.
IDENTIFICATION OF COMPONENTS Class.1 Branch pipe connection welds four inches nominal pipe size >
and greater II.
IMPRACTICAL CODE REQUIREMENTS i
The configuration-of the Reactor Coolant branch nozzle connection welds preclude complete examination.
Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum,. requires a volumetric l
and surface examination of branch pipe connection welds on piping four inches nominal pipe size and greater (Category B-J).
In particular, paragraph III-4430 requires an angle beam examination of the weld root from the weld crown.
Relief is requested from the requirements' of paragraph 111-4430-due to physical configuration of these branch nozzle connection welds.
III. BASIS FOR RELIEF Due to thc geometric configuration and slope of the weld crown, CN
~when transdt:cer contact cannot be maintained on the weld. The slope of the weld crevu' precludes examination of the weld root scanning from th; weld crown.
IV.
ALTERNATE EXAMINATION A surface examination will be performed in accordance with Code requirements. The volumetric examination of these welds will be performed to the extent practical.
O N1-002/68 2-56 Rev. O March 6, 1988
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RELIEF REQUEST NDE-10
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I.
IDENTIFICATION OF COMPONENTS Reactor Coolant Pump (1-RC-P-1A, 1-RC-P-1B and 1-RC-P-lC):
Pressure retaining welds in pump casings and pump casings II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum, requires a volumetric examination be performed during each inspection interval on 100%
of the pressure retaining welds of Category B-L-1 in at least one pump in each group of pumps performing similar functions in the system (e.g.,
reactor coolant pumps) and a visual examination of one pump casing of Category B-L-2 in each group of pumps performing similar functions in the system be performed.
III. BASIS FOR RELIEF The North Anna Power Station Unit I reactor coolant pumps are Westinghouse Model 93 controlled leakage pumps.
The Model 93 pump's casing is fabricated by velding two stainless steel castings together. Thus, there is one circumferential pressure boundary weld in the pumps that is to be examined in accordance with Category B-L-1.
(_ -
Since the installation of these pumps, it has been recognized that a volumetric examination of the casing velds is not practical with today's ultrasonic techniques.
i The physical properties of the stainless steel casting and weld material preclude a meaningful ultrasonic examination.
The capability to examine these pump casing welds in the field did not l
exist until recently. In the spring of 1981, an examination was performed on one of the reactor _ coolant pumps at the R.E.
Ginna plant using the miniature linear accelerator (MINAC), which was built under an EPRI sponsored program. This equipment has been made available to other utilities, and currently constitutes the only viable examination method for the volumetric examination of reactor coolant pump welds.
The volumetric examination method is radiographic and is performed by placing the MINAC inside the pump casing and placing film on the outside of the pump. To perform the examination, the pump must be completely disassembled, including removal of the diffuser adapter.
This amount of disassembly is far beyond the amount of disassembly performed for normal maintenance.
Insulation must also be removed from the exterior of the pump casing.
O N1-002/68 2-57 Rev. O March 6, 1988
The examination has been performed at four different sites, all of r*'s which have the Westinghouse Model 93 pump. The MINAC examination
('",)
was Performed at Ginna in the spring of 1981, at Point Beach Unit 1 in the fall of 1981, at Turkey Point Unit 3 early in 1982 and at H.
B.
Robinson Unit 2 later-in 1982. No problems with the welds were found at any of the sites.
A review of the original radiographs of the Point Beach Unit 1 pump was performed prior to the MINAC examination. and all the. landmarks found'were identified during field examination with no apparent change.
The successful performance of this volumetric examination using the MINAC at four different sites demonstrates that the method is capable of satisfying ASME Section XI examination requirements.
However, the performance of the examination has shown there is a relatively high radiation exposure associated with it.
The total exposure associated with insulation
removal, disassembly, examination and reassembly of. the pump has averaged about 40 man-rem per pump.
There have been no defects identified by the four examinations performed on these pumps to date. A volumetric examination was attempted at North Anna in 1982. A radioactive source was placed within the pump casing and film around the outside. The developed film did not meet the density requirements for an acceptable examination. This examination was attempted twice at Surry. Both examinations yielded similar results.
The pump casing examinations are also not justified from a
(~s'--)
cost / benefit perspective.
The pump disassembly, examination and reassembly is estimated to cost $750,000.
IV.
ALTERNATE EXAMINATION A visual examination of the external surfaces of one pump's casing weld and a surface examination to the extent practicable of the external casing veld of one pump will be performed to the extent and frequency of Category B-L-1.
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N1-002/68 2-58 Rev. O March 6, 1988 i
RELIEF REQUEST NDE-11 O
I.-
IDENTIFICATION OF COMPONENTS Class 1 Valve Bodies Exceeding 4 in. Nominal Pipe Size-II.
IMPRACTICAL CODE REQUIREMENTS-In Class 1 systems, valves which are greater than four inches nominal pipe size are ~ subject to visual examination. These valves vary in size, design and' manufacturer but are all manufactured-from either cast stainless steel or carbon steel.
None of the-valve bodies are welded.
Section XI of the ASME. Boiler and Pressure Vessel Code, 1983
~
Edition through the Summer ~1983 Addendum,. requires a visual' examination be performed en the internal pressure boundary surfaces of one valve in each group of valves that are of the. same constructional design and manufacturing method, and that perform similar functions in the system (Category B-M-2).
Since these examinations must be met whether or 'not the valves have to be disassembled.for maintenance, this requirement is considered impractical.
III.
BASIS FOR RELIEF The requirement to disassemble primary system valves for the sole purpose of performing a visual examination of the internal-pressure boundary surfaces has only a very small-potential of.
increasing plant safety margins and a very disproportionate-impact on expenditures of plant manpower and radiation exposure.
The performance of both carbon and stainless cast valve bodies has been excellent in PWR applications. Based on this experience and both industry and regulatory acceptance of these alloys, continued excellent service performance is anticipated.
A more practical approach that would essentially provide an equivalent sampling program and significantly reduced radiation exposurr to plant personnel is to examine the internal pressure boundary of only those valves that require disassembly for-
'l maintenance purposes.-
This would still provide a reasonable sampling of the primary system valves and give adequate' assurance that the integrity of these components is being maintained.
IV.
ALTERNATE EXAMINATION The visual examination of the internal pressure boundary surfaces will be performed, to the extent practical, when a valve is disassembled for maintenance purposes.
O N1-002/68 2-59 Rev. O March 6, 1988
. - - -, ~
RELIEF REQUEST NDE-12 f3 G
I.
IDENTIFICATION OF COMPONENTS
- Excess Letdown Heat Exchanger-(1-CH-E-4): Head-To-Flange Weld II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum, requires the excess letdown heat exchanger head-to-flange weld of Category C-A have a volumetric examination each inspection interval in accordance with subsection IWC-2500.
A full volumetric examination is not practicable.
III. BASIS FOR RELIEF The conf.'guration of the excess letdown heat exchanger head-to-flange veld is such that a full volumetric examination is impractical. The flange side slopes such that the required volume as described by figure IWC-2500-1(c) can not be fully examined.
IV.
ALTERNATE EXAMINATION A
volumetric examination will be performed to the extent practicable.
4 O
N1-002/68 2-60 Re.v. O March 6, 1988
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RELIEF REQUEST NDE-13 1.
IDENTIFICATION OF COMPONENTS Residual Heat Removal Heat Exchangers (1-RH-E-1A and 1-RH-E-1B):
Shell-To-Head Weld and Shell-To-Flange Weld II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code,.1983 Edition through the Summer 1983 Addendum, requires a volumetric examination of the Category C-A residual heat removal heat exchanger shell-to-head weld and shell-to-flange weld each inspection interval in accordance with subsection IWC-2500. A full volumetric examination is not practicable.
III. BASIS FOR RELIEF Examination of the vessel shell-to-head weld is limited by welded supports, head configuration, and weld contour. Examination of the vessel shell-to-flange weld is limited by welded supports, flange configuration, and flange bolting.
These geometric constraints and physical limitations prevent complete examination as required by figure IWC-2500-1.
IV.
ALTERNATE EXAMINATION A
volumetric examination will be performed to the extent practicable.
i O
N1-002/68 2-61 Rev. O March 6, 1988
(
RELIEF REQUEST NDE-14 I.
IDENT7.f1 CATION OF COMPONENTS Non Regenerative Heat Exchanger (1-CH-E-2):
Shell-To-Head Weld and Shell-To-Flange Weld II.
IMiRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum, requires the non-regenerative-letdown hwat exchanger shell-to-head weld and shell-to-flange veld of Category C.\\ have a volumetric examination each inspection interval in accordance with subsection IWC-2500. A full volumetric examination is not practicable.
III. BASIS FOR RELIEF Examination of both the vessel shell-to-head weld and the shell-to-flange weld is limited by the integral attachments. The integral attachments restrict the scan and prevent complete examination of the volume as required by figure IWC-2500-1.
IV.
ALTERNATE EXAMINATION A volumetric examination will be performed to the extent practicable.
i i
l l
O N1-002/68 2-62 Rev. O March 6, 1988 l
RELIEF REQUEST IGE-15 O
I.
IDENTIFICATION OF COMPONENTS Regenerative Heat Exchanger (1-CH-E-3):
Shell-To-Head Welds and Shell-to-Tubesheet Welds II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum, requires the regenerative heat exchanger shell-to-head welds and shell-to-tubesheet welds of Category C-A have a volumetric examination each inspection interval in accordance with-subsection IWC-2500.
A full volumetric examination is not practicable.
III. BASIS FOR RELIEF Examination of both the vessel shell-to-head welds and the shell-to-tubesheet welds is limited by the inlet and outlet nozzles.
The nozzles restrict the scan and prevent complete examination of the volume as required by figure IWC-2500-2.
IV.
ALTERNATE EXAMINATION A volumetric examination will be performed to the extent practicable.
O O
N1-002/68 2-63 Rev. O March 6, 1988
RELIEF REQUEST NDE-16 I.
IDENTIFICATION OF COMPONENTS Boron Injection Tank (1-SI-TK-2): Shell-To-Head 'leids II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983~
i Edition through the Sumner 1983 Addendum, requires a volumetric examination of the Category C-A boron injection tank shell-to-head welds each inspection interval in accordance with subsection IWC-2500. A full volumetric is not practicable.
III. BASIS FOR RELIEF Examination of the vessel shell-to-head welds is limited by the geometric configuration of the joint. The shell is 4.157" thick and slopes doen to a thickness of approximately 2"
where it is welded to the 2" thick vessel head.
In addition to the geometric configuration, the lower shell-to-head weld is also limited by the four integrally attached supports. The area of the weld directly under the welded supports is inaccessible for er.'aination.
IV.
ALTERNATE EXAMINATION A volumetric examination will be performed to the extent O
practicable, t
O N1-002/68 2-64 Rev. O March 6, 1988
RELIEF REQUEST NDE-17 O
1.
IDENTIFICATION OF COMPONENTS Seal Water Injection Filters (1-CH-FL-4A and 1-CH-FL-4B):
Shell-To-Flange and Shell-To-Head Welds II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum,, requires the Category C-A shell-to-flange welds and the_shell-to-head welds on the seal water injection filters be volumetrically examined each inspection interval in accordance with subsection IWC-2500.
A full volumetric examination is not practicable.
III. BASIS FOR RELIEF The configuration of the seal water inj ection filter head-to-flange weld is such that a full volumetric examination as required by figure IWC-2500-1(c) is not practical. Examination.of the shell-to-head weld is limited by the three integrally -welded supports directly over the shell-to-head weld and the 2" inlet uerzle directly above the shell-to-head weld, i
IV.
ALTERNATE PROVISIONS A volumetric examination will be performed to the extent practicable, s
1 O
l N1-002/68 2-65 Rev. 0 March 6, 1988
RELIEF REQUEST NDE-18 O
1.
IDENTIFICATION OF COMPONENTS 1
Steam Generators (1-RC-E-1A, 1-RC-E-1B, and 1-RC-E-1C):
Nozzle-To-Vessel Welds II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum, requires the steam generator nozzle-to-vessel welds of Category C-B have a surface and volumetric examination each inspection interval'in accordance with subsection IWC-2500. A full volumetric examination is not practicable.
j III. BASIS FOR RELIEF l
The physical geometry' of the three feedwater inlet nozzles prevents a full volumetric examination from being performed and insulation support brackets limit the examination of the vessel and the weld.
IV.
ALTERNATE EXAMINATION In addition to the surface examination, a volumetric examination
}
of the base material on the vessel side of the weld will be j
performed to the extent practicable.
O N1-002/68 2-66 Rev. O March 6, 1988
,... -. ~. _..
RELIEF REQUEST NDE-19
,s lN. '
I.
IDENTIFICATION OF COMPONENTS Class 2 Pressure retaining welds in piping II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME LBoiler and Pressure Vessel Code, 1983 Edition through the Summer 1983
Addendum, requires circumferential piping welds in Category C-F Item Numbers C5.21 and C5.22, be examined volumetrically and by surface examination in accordance with subsection IWC-2500 during each inspection interval. A full volumetric examination may not be practicable.
III.
BASIS FOR RELIEF Limitations from full volumetric examination may occur at geometric discontinuities such as pipe to nozzle welds, pipe to fitting welds, or fitting to fitting welds. Full volumetric examination from the fitting side of a weld would be dependent upon the geometric configuration.
Where elbows ' and tees are concerned, full volumetric examination may not be possible if the intradose prevents complete transducer contact and adequate ultrasonic coupling. No examinations can be performed from the fitting side where a valve and or flange is involved. In these
_ i cases, one hundred percent of the required volume can be examined ultrasonically.
In instances where welds occur at fitting to fitting, access restrictions as outlined above occur on both sides of the weld.
IV.
ALTERNATE PROVISIONS In addition to the surface examination, a volumetric examination will be performed to the extent practical.
l O
(_>
N1-002/68 2-67 Rev. O March 6, 1988
RELIEF REQUEST NDE-20 1..
IDENTIFICATION OF COMPONENTS Main steam header branch connection welds II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum, requires circumferential pipe br.anch connection welds in Category C-F, Item. Number C5.31, have a surface examination in accordance with subsection IWC-2500.
A surface examination of the main steam header branch connection welds is not possible.
III. BASIS FOR RELIEF The design of the main steam header branch connection velds calls for the use of a reinforcement pad. These pads are fillet welded and completely encase the branch connection welds.
IV.
ALTERNATE PROVISIONS A surface examination of the reinforcement pad's fillet welds will be performed.
O N1-002/68 2-68 Rev. O March 6, 1988 i
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RELIEF REQUEST NDE-21 O
I.
IDENTIFICATION OF COMPONENTS Outside Recirculation Spray Pumps (1-RS-P-2A-and 1-RS-P-2B):
Pump Casing Welds II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum, requires pump casing welds in Category C-G, Item Number C6.10, have a surface examination each inspection interval in accordance with subsection IWC-2500.
A surface examination of all of the pumps casing welds is not practicable.
III. BASIS FOR RELIEF Each of the two outside recirculation spray pump casings have a total of five circumferential welds and five longitudinal welds.
Three of the_circumferential welds and three of the longitudinal welds are completely encased in concrete and are not accessible for examination from the 0.D.
Of the remaining two longitudinal welds, one weld is partially encased in concrete and one weld is partially covered by a vibration plate.
0.D. examinations can be performed on both of these longitudinal welds.
The remaining two circumferential welds are completely accessible for examinations from the 0.D.
Surface examinations from the I.D.
are not a D
practicable alternative. Access into the 24" 0. D. pump casing is limited due to size constraints, the pump shaft and the pump shaft supports.
IV.
ALTERl; ATE PROVISIONS A surface examination of the accessible circumferential and longitudinal welds will be performed to the extent and frequency a
described in IWC-2500. A remote visual examination of the I.D.
of l
the pump casing welds will be performed only if the pump is disassembled for maintenance.
i
)
O N1-002/68 2-69 Rev. O March 6, 1988
RELIEF REQUEST NDE-22 rT
(
)
~'
I.
IDENTIFICATION OF COMPONENTS Low Head Safety Injection Pumps (1-SI-P-1A and 1-SI-P-1B):
Pump Casing Walds II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum, requires pump casing welds in Category C-G, Item Number C6.10, have a surface examination each inspection interval in accordance with subsection IWC-2500.
A surface examination of all of the pumps casing welds is not practicable.
III.
BASIS FOR RELIEF Each of the two low head safety injection pump casings ha"e a total of five circumferential welds and five longitudinal welds. Three of the circumferential welds and three of the longitudinal welds are completely encased in concrete and are not accessible for examination. Of the remaining two longitudinal welds, one weld is partially encased in concrete and one veld is partially covered by a vibration plate.
0.D. examinations can be performed on both of these longitudinal welds.
The remaining two circumferential welds are accessible for examinations from the 0.D.
Surface examinations
( -\\
from the I.D. are not a practicable alternative. Access into the
\\
24" 0. D. pump casing is limited due to size constraints, the pump shaft and the pump shaft supports.
IV.
ALTERNATE PROVISIONS A
surface examination of the accessible circumferential and longitudinal welds will be performed to the extent and frequency described in IWC-2500. A remote visual examination of the I.D. of the pump casing welds will be performed only if the pump is disassembled for maintenance.
N1-002/68 2-70 Rev. O March 6, 1988 4
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RELIEF REQUEST NDE-23 V}
f I.
IDENTIFICATION OF COMPONENTS Ultrasonic calibration blocks 17.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983
Addendum, gives specific requirements for the fabrication of ultrasonic calibration blocks.
Specifically, paragraph IRA-2232(a) and IWA-2232(c)(4) states:
For examination of welds, basic calibration blocks shall meet the requirements of T-434.1.1 of Article 4 and T-543 of Article 5,Section V, except that block selection shall be as follows:
(a) The material from which the blocks are fabricated shall be:
(1) a nozzle dropout from the component; (2) a component prolongation; or (3) material of the same material specification, product fo rm, and heat treatment as one of the materials ~being joined.
III. BASIS FOR RELIEF North Anna power station was constructed prior to the issuance and adoption of ASME Section XI.
Therefore, ultrasonic calibration blocks were fabricated before the guidelines of ASME Section' XI were developed and approved.
Meeting the requirements of IWA-2732(a) and IWA-2232(c)(4) of the 1983-Code would require us to manufacture new calibration blocks. Using the existing calibration blocks allows us to correlate ultrasonic data from the first-interval inspections as required by IWA-1400(h).
IV.
ALTERNATE PROVISIONS The existing ultrasonic calibration blocks will be used for the second inspection interval examinations in lieu of current code requirements.
O N1-002/68 2-71 Rev. O March 6, 1988
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RELIEF REQUEST NDE-24 b
l I.
IDENTIFICATION OF COMPONENTS All welds and areas subject to surface or volumetric examination j
l II.
IMPRACTICAL CODE REQUIREMENTS i
Section XI of the ASME Boiler and Pressure Vessel Code, 1983-Edition through the Summer 1983
Addendum, gives.
specific requirements-for identification of welds subject to surface or volumetric examination through the use of a weld reference system as outlined in IWA-2600 and Appendix III. Conforming to this requirement is impractical at this time.
III.
BASIS FOR RELIEF The second inspection interval is the first interval in which North Anna will be required to comply with a weld reference system. No other requirements for the permanent marking of welds existed prior to North Anna developing its second interval inspection program.
The requirement to mark all welds subject to surface or volumetric examination will involve scaffold erection, the removal of insulation, weld. marking, replacing insulation and removing scaffolding on hundreds of welds of which several are in high radiation areas.
IV.
ALTERNATE PROVISIONS A weld reference system will be initiated at the start of the second inspection intervs1 and those welds requiring a weld reference system will be permanently marked as they are prepared for inservice examination.
We anticipate all Class I welds requiring a surface or volumetric examination should be marked by the end of the second inspection interval. Class 2 piping welds will continually be marked as they are examined (see weld selection criteria paragraph 2.1.3, page 2-3).
O N1-002/68 2-72 Rev. O March 6, 1988
l l
lO VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UN1T 1 INSERVICE INSPECTION PROGRAM PLAN FOR COMPONENT SUPPORTS SECOND INSPECTION INTERVAL l
i O
N1-003/68 3-1 Rev. O March 6, 1988 1
____,___,.._,_,.__.__..____.__._,____.__-______..a
SECTION 3 TABLE OF CONTENTS O
3.0 INSERVICE INSPECTION PROGRAM FOR COMPONENT SUPPORTS PAGE 3.1 PROGRAM DESCRIPTION 3-3 3.1.1 Integral Attachments Examined Under the Scope of Section 2 3-3 3.1.2 Repairs and Replacements 3-3
(
3.1.3 Snubber Examinations 3-3 3.1.4 Integral Attachments Examined Under the Scope 3-3 of Section 3 3.2 PROGRAM PLAN DESCRIPTION 3-3 j
3.2.1 Inservice Inspection Progran Plan Summary 3-3 3.3 SUPPORTS EXEMPT FROM EXAMINATION AND TEST 3-4 I
3.3.1 Class 2 Exemptions 3-4 l
3.4 COMPONENT SUPPORT EXAMINATION BOUNDARY 3-3 j
3.5 INSERVICE INSPECTION PLAN TABLE - Class 1, 2, and 3 3-13 Component Supports
()
3.6 RELIEF REQUESTS 3-16 a
O N1-003/68 3-2 Rev. O March 6, 1988
T 3.0 INSERVICE INSPECTION PROGRAM FOR COMPONENT SUPPORTS
{J 3.1 PROGRAM DESCRIPTION The Inservice Inspection program for Class 1, 2 and 3 component supports meets the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through Summer 1983 Addendum, as modified by this program.
Component supports are those metal supports that ure designed to transmit loads from the component and piping to the load carrying building or foundation structures.
This shall include the attachment portion of intervening element (s) to pressure retaining components, integral and nonintegral attachments of pressure retaining components, and integral and nonintegral supports. Component supports encompass those structural elements relied upon to either support the weight of or pr; vide structural stability to components and piping.
3.1.1 All integral attachments for Class 1,
2 and 3 piping, vessels, core support structures, interior attachments to reactor vessels, and removable core support structures are included in the NDE program in Section 2.
The remaining portion of the support will be included in this prcgram.
3.1.2 Repairs and replacements shall be in accordance with Station Administrative Procedures which shall be in accordance with ASME Section XI, 1983 Edition through the Summer 1983
(T
Addendum, or later editions and addenda as may be
(,)
incorporated by reference in 10CFR50.55a, and authorized for use at North Anna Power Station in accordance with Station Technical Specification 6.8.
3.1.3 This program does not cover snubbers.
Snubbers shall be examined in accordance with Technical Specifications. The attachments of snubbers to pipes, walls, vessels, etc. will be covered by applicable Subsection IWB, IWC, or IWD.
3.1.4 Per IWF-2510(a) and (b), component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, and IWD during the first inspection interval.
For multiple components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
3.2 PROGRAM PLAN DESCRIPTION 3.2.1 The Inservice Inspection Program Plan Summary for Component Supports is presented in Section 3.5 in a tabular format.
The component supports and associated requirements are listed in descending order according to Code Category and Item Numbers. Those Categories and Item Numbers listed with "N/A" are for component supports not found at North Anna Unit 1 and are included for reference only. The following information O
is included in the tables:
N1-003/68 3-3 Rev. O March 6, 1988
q l
A.
Code Category - The Section XI Examination Category as O
defined in Table IWF-2500-1 Class 1,
2 and 3 component supports.
B.
Item Number - The Section XI Item Number as listed in Table IWF-2500-1.
All item Numbers are listed for eacn Code Category.
C.
Part Examined - The ASME Section XI description of the area to be examined.
D.
Examination Method Lists the examination method required by the provisions of ASME Section XI.
The abbreviation used is as follows:
VIS - Visual examination per IWA-2213 and 14 (reference relief request CS-1 on page 3-17)
B E.
Alternate Examination Method Lists the examination method that will be performed as an alternative to the Code required examination as stated in a relief request.
F.
Examination Requirements / Figure Number Lists the applicable Section XI figure for determining the volume of the component to be examined.
G.
Acceptance Criteria - Lists the applicable portion of O
Section XI for determining the acceptance criteria.
H.
Relief Request References a specific relief request contained in Section 3.6.
3.3 SUPPORTS EXEMPT FROM EXAMINATION AND TEST The following exemption is for ASML Class 2 component supports:
3.3.1 ISI Class 2 Exemptions EX Piping support members and piping support components that are encased in concrete.
O N1-003/68 3-4 Rev. O March 6, 1988
3.4 COMPONENT SUPPORT EXAMINATION BOUNDARY The component support examination boundaries for both integral and nonintegral supports are shown in Figures 1A &
IB.
The following definitions apply:
(a) The boundary of an integral attachment (B) connected to a pressure retaining component (A).is the distance from the pressure retaining component (A) as indicated in Figures 2A, 2B, 2C, 3 and 4.
(b) The boundary of an integral support (C) connected to a building structure (F) is the surface of the building structure.
(c) The boundary of a nonintegral support (D) connected to a pressure retaining component (A) is the contact surface between the component and the support.
(d) The boundary of a nonintegral support (D) connected to a building structure (E) is the surface of the building structure.
(e) Where the mechanical connection of a nonintegral support is buried within the component insulation, the support boundary may extend from the surface of the componeat insulation provided the support either carries the weight of the component or serves as a structural restraint in compression.
O f
(f) The examination boundary of an intervening element shall y
include the attachment portion of the intervening element to pressure retaining components, integral and nonintegral attachments of pressure retaining components, and integral and nonintegral supports.
The examination boundary does not include the attachment of the intervening element to the building structure.
(g) All integral and nonintegral connections within the boundary governed by Support Programs rules and requirements are included.
i Attachment portion includes welds, bolting, pins, clamps, etc.
OU N1-003/68 3-5 Rev. O March 6, 1988
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3-12 Rev. O March 6, 1988
s 3.5 Class 1, 2 & 3 Component Supports l
3.5.1 Examination Category F-A, Plate And Shell Type Supports 1
j ALTERNATE EXAM RELIF7 ITEM EXAM EXAM REQUIRED /
ACCEPTANCE
'iQUEST i
NO.
PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA (CS- )
F1.10 Mechanical connections to VIS, VT-3 IWF-1300-1 IWF-3410 2
l pressure retaining components l
and building structure 1
2 F1.20 Weld connections to building VIS, VT-3 IWF-1300-1 IWF-3410 structure i
i F1.30 Weld and mechanical connections VIS, VT-3 IWF-1300-1 IWF-3410 2
l at intermediate joints in
]
multiconnected integral and i
nonintegral supports F1.40 Component displacement settings VIS, VT-3 IWF-1300-1 IWF-3410' 2
of guides and stops, misalignment of supports, assembly of aupport i
items 2
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i 1
'l Rev. O N1-005f/68 3-13 March 6, 1988
I l
3.5.2 Examination Category F-B, Linear Type Supports ALTERNATE EXAti RELIEF ITEM EXAM EXAM REQUIRE /
ACCEPTANCE REQUEST t NO.
PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA' (CS- )
F2.10 Mechanical connections to VIS, VT-3 IWF-1300-1 IWF-3410 2.
pressure retaining components I
and building structure F2.20 Weld connections to building VIS, VT-3 IWF-1300-1 IWF-3410 2
structure 1
F2.30 Weld and mechanical connections VIS, VT-3 IWF-1300-1 IWF-3410 2
at intermediate joints in multiconnected integral and i
nonintegral supports F2.40 Component displacement settings VIS, VT-3 IWF-1300-1 IWF-3410 2
of guides and stops, misalignment of supports, assembly of support 3
j items i
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O 3.5.3 Examination Category F-C, Component Standard Supports ALTERNATE EXAM RELIEF EXAM EXAM REQUIRE /
ACCEPTANCE REQUEST NO.
PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA (CS- )
F3.10 Mechanical connections to VIS, VT-3 IWF-1300-1 IWF-3410 2
pressure retaining components j
and building structure i
i F3.20 Weld connections to VIS, VT-3 IWF-1300-1 IWF-3410 2
l building structure i
F3.30 Weld and mechancial connections VIS, VT-3 IWF-1300-1 IWF-3410 2
3 4
at intermediate joints in
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multiconnected integral and nonintegral supports F3.40 Component displacement settings VIS, VT-3 IWF-1300-1 IWF-3410 2
of guides and stops, misalignment of supports, assembly of support items F3.50 Spring type supports, constant
- VIS, VT-4 VIS, VT-3 IWF-1300-1 IWF-3410 1,2 l
load type supports, shock absorbers, hydraulic and mechanical type snubbers l
I N1-005f/68 3-15 Rev. O March 6,i1988
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I' 3.6 Inservice Inspection Program Relief Requests.
t The following relief requests identify those ASME'Section XI ' Code -
requirements considered to be impractical. The basis for the relief 4
request and the alternate testing to be performed'is given.
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,'t RELIEF REQUEST NO. CS-1 s.
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IDENTIFICATION OF COMPONENTS lWA-2214 VT-4 Examinations II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum, describes visual examinations in IWA-2210 of the Code.
Examination VT-3 (IWA-2213) and examination VT-4 (IWA-2214) are utilized for inspection as described in subsection IWF Table 2500-2 for Category F-C supports.
Relief is requested from the requirement of a VT-4 examination (IWA-2214) due to unnecessary and impractical duplication.
III. BASIS FOR RELIEF The VT-4 examination is only required for support examinations on Category F-C components (spring hanger, snubber etc.),
where operability and functional adequacy need to be determined.
It was recognized by the Code that these examinations (VT-3, VT-4) were closely related, and generally performed by the same individual qualified to each discipline. Although not endorsed in 10CFR50.55a, f-g the Winter 1984 Addendum of the Code combined the VT-3 and VT-4
()
examinations to a singular VT-3 examination. Applying this reduction administratively would reduce qualification documents, examination records, review requirements, and reporting without eliminating the intent of the examination.
IV.
ALTERNATE PROVISIONS It is proposed that the definition of a VT-3 examination as written in the Winter 1984, Addendum be substituted for the current VT-3 and VT-4 requirement:
a) The VT-3 visual examination.shall be conducted to determine the 1
'ondition of components and general mechanical and structural c
their supports, such as the verification of clearances, settings, physical displacements, loose or missing parts, debris,, corrosion, wear, erosion, or the loss of integrity at bolted or welded connections.
b) The VT-3 examination shall include examinations-for conditions that could affect operability or functional adequacy of snubbers, J
and constant load and spring type supports.
c) For. component supports and component interiors, the visual examination may be performed remotely with or without optical aids to verify the structural integrity of the component.
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March 6, 1988 J
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RELIEF REQUEST NO. CS-2
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IDENTIFICATION OF COMPONENTS Class 1 and Class 3 Component Supports II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer 1983 Addendum, requires a volumetric or surface examination of Class 1 integral attachments and a visual examination of Class 3 integral attachments. Relief is requested from examination of those integral attachments considered inaccessible.
III. BASIS FOR RELIEF IWC-1230 exempts piping support members and piping support components that are encased in concrete from the examination requirements set forth in IWC-2500.
It is requested that this exemption be expanded to include those Class 1 and Class 3 integral attachments of Categories B-K-1, D-A, D-B and D-C which are encased in concrete and inaccessible for examination.
IV.
ALTERNATE PROVISIONS None.
O N1-003/68 3-18 Rev. O March 6, 1988
,_.._-__.__._-.__.._.__,.__..___.._..-._.._..,..._,....____._......U
O VIRGINIA ELECTRIC AND F0WER COMPANY NORTH ANNA POWER STATION UNIT 1 l
O INSERVICE INSPECTION PROGRAM FOR SYSTEM PRESSURE TESTS i
SECOND INSPECTION INTERVAL N1-004a Rev. 0 4-1 March 6, 1988
O SECTION 4 TABLE OF CONTENTS 4.0 SYSTEM PRESSURE TESTS PROGRAM PLAN PAGE
4.1 INTRODUCTION
4-3
[
4.2 PROGRAM DESCRIPTION 4-4 4.3 SYSTEM PRESSURE TESTS 4.3.1 Class 1 Components 4-5 4.3.2 Class 2 Components 4-8 4.3.3 Class 3 Components 4-9 4.3.4 Notes 4-10 4.4 SYSTEM PRESSURE TEST PROGRAM RELIEF REQUESTS 4-14 O
O-N1-004a Rev. 0 4-2 March 6, 1988
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SYSTEM PRESSURE TESTS PROGRAM PLAN 4.0
)
4.1 INTRODUCTION
4
.This System Pressure Test Program is applicable to the North Anna j
Power Station Unit 1.
This program covers the system pressure test requirements for ASME Class 1, 2 and 3 components. The development, implementation and administration of the program for each Class is
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detailed in subsequent sections.
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N1-004a Rev. 0 4-3 March 6, 1988
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4.2 PROGRAM DESCRIPTION I
The North Anna Unit 1 System Pressure Test Program is in accordance with the ASME Boiler and Pressure Vessel Code Section XI, 1983 Edition, Summer of 1983 Addendum inclusive. The principles and guidelines established by this Code shall be adopted while conducting system pressure tests except in cases where relief has been requested and provided within this document.
Relief requests will identify the specific deviation frca code requirements and provide an alternative testing arrangement.
This program will be officially implemented by June 6,1988 and will govern testing for the Unit 1 second incervice inspection interval which ends June 6, 1998. The program will be updated as' required by changes in plant configuration, relief requests, etc.
Prior to the end of the second inservice inspection interval, the program will be reviewed and upgraded to assure continued compliance with 10CFR50.55a(g)(4) for the third inservice inspection interval.
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N1-004a Rev. 0 a
4-4 Ma':h 6, 1988 4
l
Ci 4.3 SYSTEM PRESSURE TESTS The System Pressure Test summary for the Component Program is presented in Sections 4.3.1, 4.3.2 and 4.3.3 in a cabular format.
The components and associated requirements are listed in descending order according to Code Category and Item Numbers. Those Categories and Item Numbers listed with "N/A" are for components not found at North Anna Unit 1 and are included for reference only. The following information is included in the tables.
A.
Code Category - The Section XI Examination Category as defined in Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1 for Class 1, 2, and 3 compcnents.
B.
Item Number - The Section XI Item Number as listed in Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1.
C.
Part Examined The ASME Section XI description of the area to be examined.
j D.
Exam or Test Requirement - The ASME Section XI examination or i
test requirement.
l E.
Exam Method - The examination method required by the provisions of ASME Section X1.
l (' '
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Acceptance Standard - The applicable article of Section XI for determining the acceptance standard or the actual standard.
G.
Schedule the schedule for examinations or tests for the current inservice inspection interval.
H.
Notes - Notes are in Section 4.3.4.
I I.
Relief Request - References a request contained in Section 4.4.
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N1-004a Rev. 0 4-5 March 6, 1988
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4.3.1 CLASS 1 COMPONENTS (10 YEAR SCHEDULE) 4.3.1.1 EXAMINATION CATEGORY B-E, PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS l
RELIEF j
ITEM PARTS TO BE EXAM EXAM ACCEPTANCE REQUEST l
NO.
BE EXAMINED REQUIREMENT MET 110D STANDARD SCHEDULE NOTES (SPT- )
l l
B4.11 PARTIAL PENETRATION EXTERNAL VISUAL IWA-5250 CONDUCTED DURING SYSTEM 2,5 l
VESSEL N0ZZLES SURFACE VT-2 HYDROSTATIC TEST 1
B4.12 PARTIAL PENETRATION EXTERNAL VISUAL IWA-5250 CONDUCTED DURING SYSTEM 2,5 CONTROL ROD DRIVE SURFACE VT-2 HYDROSTATIC TEST N0ZZLES B4.13 PARTIAL PENETRATION EXTERNAL VISUAL IWA-5250 CONDUCTED DURING SYSTEM 2,5 5
INSTRUMENTATION N0ZZLES SURFACE VT-2 HYDROSTATIC TEST B4.20 PRESSURIZER HEATER EXTERNAL VISUAL IWA-5250 CONDUCTED DURING SYSTEM 2,5 PENETRATION WELDS SURFACE VT-2 HYDROSTATIC TEST NI-004b/68 4-6 Rev. O March 6, 1988
O O
O 4.3.1.2 EXAMINATION CATEGORY B-P, PRESSURE RETAINING COMPONENTS RELIEF ITEM PARTS TO BE TEST EXAM ACCEPTANCE REQUEST NO.
BE EXAMINED REQUIREMENT METHOD STANDARD SCHEDULE NOTES (SPT- )
B15.10 REACTUR VESSEL.
SYSTE!!
VISUAL.
IWA-5250 EACH REFUELING 1,5 5
PRESSURE RETAINING LEAKAGE TEST, VT-2 OUTACE BOUNDARY IWB-5221 BIS.Il REACTOR VESSEL, SYSTEM VISUAL.
IWA-5250 ONE TEST 1,2,5 5
PRESSURE RETAINING HYDROSTATIC VT-2 BOUNDARY TEST. IWB-5222 B15.20 PRESSURIZER, PRESSURE SYSTEM
VISUAL, IWA-5250 EACH REFUELING 1,5 RETAINING BOUNDARY LEAKAGE TEST.
VT-2 OUTAGE IWB-5221 B15.21 PRESSURIZER, PRESSURE SYSTEM
VISUAL, IWA-5250 ONE TEST 1,2,5 RETAINING BOUNDARY HIP.0 STATIC VT-2 TEST. IWB-5222 B15.30 STEAM GENERATORS, SYSTEM
VISUAL, IWA-5250 EACH REFUELING 1,5 13 PRESSURE RETAINING LEAKAGE VT-2 OUTAGE BOUNDARY TEST IWB-5221 B15.31 STEAM GENERATORS, SYSTEM
VISUAL, IWA-5250 ONE TEST 1,2,5 13 PRESSURE RETAINING HYDROSTATIC VT-2 BOUNDARY TEST, IWB-5222 B15.40 HEAT EXCHANGERS, N/A N/A N/A N/A N/A PRESSURE RETAINING BOUNDARY N1-004b/68 4-7 Rev. O March 6, 1988
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l 4.3.1.2 EXAMINATION CATEGORY B-P, PRESSURE RETAINING COMPONENTS (Con't.)
RELIEF ITEM PARTS TO BE TEST EXAM ACCEPTANCE REQUEST NO.
BE EXAMINED REQUIREMENT MET 110D STANDARD SCIIEDULE NOTES (SPT- )
B15.41 liEAT EXCilANGERS, N/A N/A N/A N/A N/A PRESSURE RETAINING BOUNDARY B15.50 PIPING, PRESSURE SYSTEM VISUAL.
IWA-5250 EACli REFUELING 1,3,5 7
RETAINING BOUNDARY LEAKAGE VT-2 01.TAGE TEST, IWB-5221 B15.51 PIPING, PRESSURE SYSTEM
VISUAL, IWA-5250 ONE TEST 1,2,5 1,2,6,8 PRESSURE RETAINING HYDROSTATIC VT-2 BOUNDARY TEST, IWB-5222 B15.60 PUMPS, PRESSURE SYSTEM
VISUAL, IWA-5250 EACil REFUELING 1,5 RETAINING BOUNDARY LEAKAGE VT-2 OUTAGE TEST, IWB-5221 B15.61 PUMPS, PRESSURE SYSTEM
VISUAL, IWA-5250 ONE TEST
],2,5 1
RETAINING BOUNDARY FYDR0 STATIC VT-2 TEST, IWB-5222 B15.70 VALVES, PRESSURE SYSTEM
VISUAL, IWA-5250 EACil REFUELING 1,3,5 7
RETAINING BOUNDARY LEAKAGE VT-2 OUTAGE TEST, IWB-5221 B15.71 VALVES, PRESSURE SYSTEM
VISUAL, IWA-5250 ONE TEST 1,2,5 2,6,8 RETAINING OUNDARY llYDR0 STATIC VT-2 TEST IWB-5222 N1-004b/68 4-8 Rev. O March 6, 1988 m-.
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4.3.2 CLASS 2 COMPONENTS (10 YEAR SCllEDULE) 4.3.2.1 EXAMINATION CATEGORY C-II, PRESSURE RETAINING COMPONENTS RELIEF ITEM PARTS TO BE TEST EXAM ACCEPTANCE REQUEST NO.
BE EXAMINED REQUIREMENT METilOD STANDARD SCHEDULE NOTES (SPT- )
C7.10 PRESSURE VESSELS, SYSTEM
VISUAL, IWA-5250 ONCE PER 4,5,6 PRESSURE RETAINING FUNCTIONAL VT-2 INSPECTION COMPONENTS TEST, IWC-5221 PERIOD C7.20 PRESSURE VESSELS, SYSTEM
VISUAL, IWA-5250 ONE TEST 2,4,5,6 11 PRESSURE RETAINING HYDROSTATIC VT-2 COMPONENTS TEST, IWC-5222 C7.30 PIPING, PRESSURE SYSTEM
VISUAL, IWA-5250 ONCE PER 4,5 RETAINING COMPONENTS FUNCTIONAL VT-2 INSPECTION TEST, IWC-5221 PERIOD C7.40 PIPING, PRESSURE SYSTEM
VISUAL, IWA-5250 ONE TEST 2,4,5,7 3,9, RETAINING COMPONENTS HYDROSTATIC VT-2 10,11 TEST, IWC-5222 C7.50 PUMPS, PRESSURE SYSTEM VISUAL.
IWA-5250 ONCE PER 4,5 RETAINING COMPONENTS FUNCTIONAL VT-2 INSPECTION TEST. IWC-5221 PERIOD C7.60 PUMPS, PRESSURE SYSTEM
VISUAL, IWA-5250 ONE TEST 2,4,5 RETAINING COMPONENTS IlYDR0 STATIC VT-2 TEST, IWC-5222 C7.70 VALVES, PRESSURE SYSTEM
VISUAL, IWA-5250 ONCE PER 4,5 RETAINING COMPONENTS FUNCTIONAL VT-2 INSPECTION TEST, IWC-5221 PERIOD C7.80 VALVES, PRESSURE SYSTEM
VISUAL, IWA-5250 ONE TEST 2,4,5,7 3,9, RETAINING COMPONENTS IlYDROSTATIC VT-2 10,11 COMPONENTS TEST, IWC-5222 N1-004b/58 4-9 Rev. O March 6, 1988
O O
O 4.3.3 CLASS 3 COMPONENTS (10 YEAR SCinEDULE) 4.3.3.1 EXAMINATION CATEGORY D-A, SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION RELIEF ITEM PARTS TO BE TEST EXAM ACCEPTANCE REQUEST NO.
BE EXAMINED REQUIREMENT METHOD STANDARD SCllEDULE NOTES (SPT- )
DI.10 PRESSURE RETAINING SYSTEM
VISUAL, NO LEAKAGE ONCE PER 5,6,8 COMPONENTS INSERVICE VT-2 INSPECTION TEST, IWD-5221 PERIOD DI.10 PRESSURE RETAINING SYSTEM
VISUAL, NO LEAKAGE ONE TEST 2,5,6,8 COMPONENTS HYDROSTATIC VT-2 TEST, IWD-5223 N1-004b/68 4-10 Rev. 0 l
March 6, 1988 r
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1 4.3.3.2 EXAMINATION CATEGORY D-B SYS1 EMS IN SUPPORT OF EMERCENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATHOSPHERE CLEANUP, AND REACTOR RESIDUAL HEAT REMOVAL 1
i RELIEF l
ITEM PARTS TO BE TEST EXAM ACCEPTANCE REQUEST NO.
BE EXAMINED REQUIREMENT METHOD STANDARD SCHEDULE NOTES (SPT- )
I f
D2.10 PRESSURE RETAINING SYSTEM
VISUAL, NO LEAKAGE ONCE PER 5,6,8 l
COMPONENTS INSERVICE VT-2 INSPECTION
)
TEST, IWD-5222 PERIOD 4
f D2.10 PRESSURE RETAINING SYSTEM
VISUAL, NO LEAKAGE ONE TEST 2.5,6, 4
COMPONENTS HYDROSTATIC VT-2 8
l TEST, IWD-5223 i
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March 6, 1988 i
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- i 4.3.3.3 EXAMINATION CATEGORY D-C, SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM SPENT FUEL STORAGE POOL RELIEF ITEM PARTS TO BE TEST EXAM ACCEPTANCE REQUEST
' i NO.
BE EXAMINED T~QUIREMENT METHOD STANDARD SCHEDULE NOTES (SPT- )
t D3.10 PRESSURE RETAINING SYSTEM
VISUAL, IWA-5250 ONCE PER 5,6,8 COMPONENTS INSERVICE VT-2 INSPECTION TEST, IWD-5221 PERIOD D3.lO PRESSURE RETAINING SYSTEM
VISUAL, IWA-5250 ONE TEST 2.5,6,8 COMPONENTS HYDROSTATIC VT-2 1
TEST IWD-5223 l
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4.3.4 NOTES
. 'd Note 1 Class 1 systems are identified on the Classification Boundary Drawings listed in the Abstract.
These systems are designated as shown on 11715-CBM-LaS-2.
Note 2 Class 1,
2 and 3 system hydrostatic tests shall be conducted near the end of the second interval within the last period.
This coincides with the tests conducrod during the first inspection interval.
Note 3 The piping between the following valves will be tested prior to departing het shutdown conditions when exiting a rafueling shutdown. The piping is normally pressurized to 660 psig.
1-SI-127 AND 1-SI-125. HCV-1850B 1-SI-144 AND 1-SI-142, HCV-1850D, MOV-1720A 1-SI-161 AND 1-SI-159, HCV-1850F, MOV-1720B Ncee 4 Class 2 systems are identified on the Classificiation Boundary Drawings listed in the Abstract.
Class 2 systems are designated as shown on 11715-CBM-L&S-2.
Note 5 This station will use the following guidance for O
determining the completion of scheduled system pressure tests (i.e. Category B-E, B-P, C-H, D-A, D-B, D-C):
a) The tests which meet the pressure, temperature, hold time and VT-2 examination requirements as stipulated in the Code will be treated as complete for scheduled inspection purposes.
b) Any discrepancies will be treated in accordance with IWA-5250 and the station's Repair / Replacement Program.
c) Weld leaks and excessive mechanical leaks will be addressed through a station engineering evaluation to determine continued operability. This does not apply to repair / replacements which must exhibit no leakage at the area of examination of the repair / replacement.
4 O
N1-004c/68 4-13 Rev. O March 6, 1988
Note 6 Visuel Examination of Heat Exchangers will be conducted using the following methods:
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a) When pressurizing the tube side of a heat exchanger, the tube integrity will be checked by u
the following methods:
1) Fill and vent the shell side of the heat
)
j exchanger prior to the test and monitor an l
open vent path on the shell side during l
pressurization for overflow.
2) Any overflow will be an indication of leakage.
l
3) A drain method can be used by draining the shell side and observing leakage out the open I
drain path on the shell side.
b) When pressurizing the shell side of a heat i
exchanger, the tube integrity can be checked by the following methods:
1) Fill and vent the tube side of the heat exchanger prior to pressurization.
2) Monitor an open vent path on the tube side for overflow.
3) Any overflow will be an indication of leakage.
V The required visual examination of the heat exchanger will be considered complete using either method above.
Any discrepancies will be referred to the station's Repair / Replacement Program.
Note 7 For identification purposes, piping exteading beyond the valves listed below on Classification Boundary Drawing 11715-CBM-092A, Sheet 1 of 2 will be l
considered open ended and in accordance with the i
requirements of IWC-5222(d) for test purposes.
VALVE PIPING 1-LM-1 3/8"-LM-3-ICN6-Q2 1-LM-5 3/8"-LM-1-ICN6-Q2 1-LM-10 3/8"-LM-2-ICN6-Q2 1-LM-15 3/8"-LM-10-ICN6-Q2 Note 8 Class 3 Systems are identified in the Classification Boundary Drawings listed in the Abstract.
These systems are designated as shown on 11715-CBM-L&S-2.
['o N1-004c/68 4-14 Rev. O March 6, 1988
i I
i 4.4.
SYSTEM PRESSURE TEST RELIEF REQUESTS i
.i The following relief requests identify code requirements which i
are impractical for North Anna Unit 1 and provide justification 1
for the requested exception.
Where appropriate, alternate testing to be performed in lieu of the code requirements is proposed.
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i N1-004c/68 4-15 Rev. O March 6, 1988
4 RELIEF REQUEST SPT-1 I.
IDENTIFICATION OF COMPONENTS System
- Chemical and Volume Control Components: Piping on drawing 11715-CBM-0950, Sheet 2_of 2, between the pumps and the first flanges from the pumps listed below.
PUMP LINE 1-RC-P-1A 2"-CH-14-1502 1-RC-P-1B 2"-CH-15-1502 1-RC-P-1C 2"-CH-16-1502 Class 1
II.
IMPRACTICAL CODE REQUIREMENTS System Hydrostatic Test per IWB-5222 III. BASIS FOR RELIEF Pressurizing the piping listed above will also pressurite the number one seal of the reactor coolant pumps.
This could potentially i
damage the number one seal.
IV.
ALTERNATE TESTING The normal system leakage test after each refueling is an adequate l
examination.
l NOTE: Relief was granted to Surry Power Station Unit 2 per Safety Evaluation Report dated 01/24/86 for the same situation as described above.
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O N1-004d/68 4-16 Rev. O March 6, 1988 1
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i RELIEF REQUEST SPT-2
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I.
IDENTIFICATION OF COMPONENTS
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System
Chemical and Volume Control Components: Piping located on drawing 11715-CBM-095C, Sheet 1 of 2, between the valves listed below.
VALVES LINE 1-CH-328 and HCV-1311 2"-CH-68-1502 1-CH-325 and 1-CH-496 2"-CH-1-1502 Class 1
II.
IMPRACTICAL CODE REQUIREMENTS Class 1 System Hydrosta*.ic Test per IWB-5222.
Po=2500 psig, To=496*F, Test Pressure is 25!0 psig per IWB-5222.
III. BASIS FOR RELIEF Check valves 1-CH-328 and 1-CH-325 prevent the compenents listed above from being pressurized without pressurizing the reactor O
coolant system. The code required test pressure of 2550 psig will overpressurite the reactor coolant system.
Also, the power operated relief valves (PCV-1456 and PCV-1455C) of l
1 the reactor coolant system are designed to limit the pressurizer i
pressure to a v11ue below the fixed high-pressure reactor trip l
setpoint (2385 psig). The relief valve setpoints are 2335 psig.
It is not desirable to take the reactor coolant system above the power 4
operated relief valve setpoint.
IV.
ALTERNATE TESTING As an alternative, the reactor coolant system will be pressurized to i
a pressure as close as practical to 2335 psig but not less than 2300 psig while the reactor is in a shutdown condition to create a pressure boundary at check valves 1-CH-328 and 1-CH-325.
The components listed above will then be tested to a pressure (2300 psig
< test pressure < 2335 psig) as close as practical to the reacter coolant system pressure using a charging pump.
Note: Similar relief was granted to Surry Power Station Unit 2 per Safety Evaluation Report dated 01/24/86 for components with the same design configuration.
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N1-004d/68 4-17 Rev. O March 6, 1988 q
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RELIEF REQUEST SPT-3
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IDENTIFICATION OF COMPONENTS System-
Chemical and Volume Control l
Components: Piping located on drawing 11715-CBM-095C, Sheet 1 of 2, I
between the valves listed below, i
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VALVES LINES 1-CH-496, HCV-1311 3/4"-CH-240-1502 y
and MOV-1289A 2"-CH-68-1502 3"-CH-1-1502 3"-CH-79-1502 Class
2 II.
IMPRACTICAL CODE REQUIREMENTS g
Class 2 System Hydrostatic Test per IWC-5222. Since there are no relief valves for the above components, test pressure per IWC-5222 is 3419 psig.
I III. BASIS FOR RZLIEF Check Valves 1-CH-328, 1-CH-325 and 1-CH-496 prevent the components
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listed above from being pressurized without pressurizing the.sreactor coolant system.
The Code required test pressure of 3419 psig will overpressurize the reactor coolant system.
Also, the power operated relief valves (PCV-1456 and PCV-1445C) of the reactor coolant system are designed to limit the pressurizer pressure to a value below the fixed high-pressure reactor trip setpoint (2385 psig). The relief valve setpoints are 2335 psig. It is not desirable to take the reactor coolant system above the power operated relief valve setpoint.
IV.
ALTERNATE TESTING
- As an alternative, the reactor coolant system will be pressurized to a pressure as close as practical to 2335 poig but not less than 2300 psig while the reactor is in a'
shutdown condition to create a pressure boundary at check valves 1-CH-328 and 1-CH-496.
The components listed above will then be tested to a pressure (2300 psig.
< test pressure < 2335 psig) as close as practical to the reactor coolant system pressure using a charging pump.
O N1-004d/68 4-18 Rev. O March 6, 1988
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IDENIIFICATION OF COMPONENTS r
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N aponents: Piping located on drawing 11715-CdM-0MA, Sheet 1 of 3, i
between the valves listed below.-
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j VALVE CONNECT 1NC LTNES VALVE 1-W-6 2 3"-VAPD-10-601 i
to 3"- b'a /D-9-(01 1-W-68 f) t; 1-FR*64 3"-WAINb-601 '
1-FW- $N 5
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1-W-9 3 3" 'd rPL12-601 i
to 3"lW'APD-11-601/ '1-$W-100 1-W-9 6 3"-WAIL 01-6f
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f 1-W-126 3"-VAP9'14-601 to '3" f,',APD-13-601
'1-W-132
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[ 1-W-120 3'-WAPD-13 601 1-W-132 i
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.4"-V PD-39'-601
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3
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IMPPACTICM. CODE REQUIREMENTS /
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Class 3 System Hydrostatic Test per IWD-5223 and IWA-5213fd7.','
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P = 400 psig, Td < 200*F Tes: Pressure is 1540 psig pel IWD-5223.
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III. BASIS FOR RELIEF r
j
.s Due to. check valves 1-W-13 2,
1-FW-100,,and 1-W-68, the piping listed dove cannot be pressurized without pressurizing the steam generators.
'Th-code required test pressure of 1540 psig would overprr.esurize the steam generaters.
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March 6, 1988
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1 RELIEF REQUEST SPT-4 (Cont.)
IV.. ALTERNATE TESTING Since the components listed above cannot be pressurized without R-pressurizing the steam generators, they must be tested per the required manufacturer's hydrostatic test method for the steam generators.
Therefore, the proposed alternative examination is the examination described in the Westinghouse Technical Manual fori-the secondary side of the steam generators.
The examinationtis to pressurize the secondary side of the steam generators to 1356 psig, hold for 30 minutes, and then reduce to the design pressure (1085 psig) for 3 1/2 hours. A VT-2 exan.ination will then he pc: formed.
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s N1-004d/68 4-20 Rev. O March 6, 1988
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c RELIEF REQUEST SPT-5 m
V I.
IDENTIFICATION 0F COMPONENTS' r -,
3 System
Reactor Coolant Components: Bottom of reactor vessel
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+
Class I
c II.
IMPRACTICAL CODE REQUIREMENTS Class 1 System Hydrostatic Test, IWB-5222 Class 1 System Leakage Test, IWB-5221 Visual Examination,'IUA-5240 III.
BASIS FOR RELIEF Primary leakage detection using Code described visual detection techniques would be limited in usefulness and hazardous'to conduct.
During_ the time the primary system.
is at test
pressure, environmental and subatmospheric conditions. restrict the area '
required to be accessed for visual inspection.
IV.
ALTERNATE TESTING The proposed alternative examination is to examine the bottom of the reactor vessel for evidence of leakage during-the 10 year vessel examination.
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1 RELIEF REQUEST SPT-6
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I.
IDENTIFICATION OF COMPONENTS 3
System
Residual Heat Removal Components: Piping located on drawing 11715-CBM-094A, Sh'eet 1 of 2, between the valves listed below.
VALVES' LINE MOV-1700 and MOV-1701 14"-RH-1-1502 Class 1
II.
IMPRACTICAL CODE REQUIREMENTS Class 1 System Hydrostatic Test IWB-5222. Po=2235 psig, To=650*F, Test pressure per IWB-5222 is 2280 psig, i!
III. BASIS FOR RELIEF l
During the system hydrostatic test of the primary system, MOV-1700 is closed in addition to MOV-1701 in order to prevent possible overpressurization of the residual heat removal system.
Thus, the portion of the RHR system identified above cannot be pressurized with the primary system and due to design, it cannot be pressurized O
without opening one of the MOV's.
IV.
ALTERNATE TESTING As an alternative, the components listed above will be tested in accordance with IWC-5222 during the hydrostatic test administered to line 14"-RH-2-602.
The test pressure will be 584 psig as determined j
by the setpoint of relief valves RV-1721A and RV-1721B.
This alternative is considered sufficient since the relief valves are set i
at 467 psig. As a result, line 14"-RH-1-1502 should not see a pressure significantly higher than 467 psig. In addition, MOV-1700 and MOV-1701 will not open if the reactor coolant pressure is > 660 psig.
O N1-004d/68 4-22 Rev. O March 6, 1988
i-RELIEF REQUEST SPT-7 iL O
I.
IDENTIFICATION OF COMPONENTS l
System
-Residual Heat Removal
[
Components: Piping located on drawing.11715-CBM-014A, Sheet 1 of 2, between the valves listed below, j
VALVES LINE MOV-1700 and MOV-1701 14"-RH-1-1502 Class 1
A II.
IMPRACTICAL CODE REQUIREMENTS Class 1 System Leakage Test, IWB-5221 j
III.
BASIS FOR RELIEF The system leakage test conducted on the prir.ary system is done with
{
both MOV-1700 and MOV-1701 closed for reasons expounded previously in Relief Request SPT-6.
This prevents pressurization of MOV-1701 and piping between the two MOV's.
IV.
ALTERNATE TESTING As an alternative, during the performance of the Class 2 functional test on line 14"-RH-2-602, MOV-1701 will be open as well as MOV-1700.
This piping will be examined to the normal VT-2 requirements at the functional test conditions.-
I B
O N1-004d/68 4-23 Rev. O March 6, 1988
i l
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RELIEF REQUEST SPT-8 I.
IDENTIFICATION OF COMPONENTS System
Safety Injection Components: Piping located on drawing 11715-CBM-096B, Sheet 4 of 4, between the valves listed below.
VALVES LINES 1-SI-83, 1-SI-190 and 1-SI-195 6"-SI-131-1502 1-SI-86, 1-SI-192 and 1-SI-197 6"-SI-133-1502 1-SI-89, 1-SI-194 and 1-SI-199 6"-SI-132-1502 s
1-SI-95, 1-SI-211 and 1-SI-204 6"-SI-19-1502 2"-SI-59-1502 1-SI-99, 1-SI-209 and 1-SI-203 6"-SI-21-1502 2"-SI-61-1502 1-SI-103, 1-SI-213 and 1-SI-205 6"-SI-16-1502 2"-SI-63-1502 Class
1 k
II.
IMPRACTICAL CODE REQUIREMENTS Class 1 System Hydrostatic Test per IWB-5222.
Po=2235 psig, To=160*F, Test Pressure per IWB-5222 is 2432 psig.
III.
BASIS FOR RELIEF The first valve in each set prevent the components listed above from being pressurized without pressurizing the reactor coolant system, i
The power operated relief valves (PCV-1456 and PCV-1455C) of the reactor coolant system are designed to limit the pressurizer pressure to a value below the fixed high-pressure reactor trip setpoint (2385 psig).
The relief valve setpoints are 2335 psig which is below the test pressure of 2432 psig. It is not desirable to take the reactor coolant system above the power operated relief valve setpoint.
l N1-004d/68 4-24 Rev. O March 6, 1988
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RELIEF REQUEST SPT-8 (Cont.)
IV.
ALTERNATE TESTING As an alternative, the reactor coolant system will be pressurized to a pressure as close as practical to 2335 psig but not less than 2300 psig while the reactor is in a shutdown condition to create a pressure boundary at the first valve of each set listed above.
These components will then be tested to a pressure (2300 psig < test pressure < 2335 psig) as close as practical to the reactor coolant system pressure using a charging pump. The reactor coolant system will be borated to a concentration equal to or greater than cold shutdown boron concentration.
Note: Similar relief was granted to Surry Power Station Unit 2 per Safety Ev;1uacios. Report dated 01/24/86 for components with the samt design.
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N1-004d/68 4-25 Rev. O i
March 6, 1988 1
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I.
IDENTIFICATION OF COMPONENTS p
System
Safety Injection t
i Components: Pip'ing and. valves located on' drawings' 11715-CBM-096A,-
Sheet 2 of" 3, and 11715-CBM-096B, Sheet 4 of 4, listed below.
d VALVE CONNECTING LINE VALVE MOV-1890C and 10"-SI-18-1502/
MOV-1890D 10"-SI-238-1502 to 6"-SI-133-1502 ~ '1-SI-197 to 6"-SI-132-1502 1-SI-199 to 6"-SI-131-1502 1-SI-195 MOV-1890A 10"-SI-15-1502 to 6"-SI-16-1502 1-SI-213 to 6"-SI-130-1502 1-SI-211 to 6"-SI-19-1502 MOV-1890B 10"-SI-140-1502 to 6"-SI-21-1502 1-SI-209
()
1-SI-193 2"-SI-55-1502 1-SI-194 1-SI-191 2"-ST-53-1502 1-SI-192 1-SI-188 2"-SI-51-1502 1-SI-190 Class
2 II.
IMPRACTICAL CODE REQUIREMENTS 2485 psig, Class 2 System Hydrostatic Test per IWC-5222.
P
=
d Design Temperature is less than 200'F, Test pressure is 2733.5 psig.
III. BASIS FOR RELIEF Check valves 1-SI-83, 1-SI-86, 1-SI-89, 1-SI-95, 1-SI-99 and 1-SI-103 prevent the components listed above from being pressurized without pressurizing the reactor coolant systea. The Code required test pressure of 2733.5 psig will ove.rpressurize the reactor coolant system.
The power operated relief valves (PCV-1456 and PCV-1455C) of the reactor coolant system are designed to limit the' pressurizer pressure to a value below the fixed high-pressure reactor trip setpoint (2385 psig). The relief valve setpoints are 2335 psig which is below the test pressure of 2733.5 psig.
It is not desirable to take the reactor coolant system above the power operated relief valve setpoint.
O N1-004d/68 4-26 Rev. O March 6, 1988
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,IV. ALTERNATE TESTING As an alternative, the reactor coolant system will be pressurized to a pressure as close as practical to 2335 psig but not less than 2300 psig while t!!e reactor is in a shutdown condition to create a pressure' boundary at Check Valves 1-SI-83, 1-31-86, 1-SI-89, 1-SI-95, 1-SI-99 and 1-SI-103.
These components will then be tested to a pressure (2300 psig < test pressure < 2335 psig) as close as practical to the reactor coolant system pressure using a test pump.
4 Note: Similar relief was granted to Surry Power Station Unit 2 per Safety Evaluation Report dated 01/24/86 for components with the same design configuration.
O l
_N1-004d/68 4-27 Rev. O Mauch 6,1988
RELIEF REQUEST SPT-10 I.
IDENTIFICATION OF COMPONENTS System Safety Injection Components: Piping located on drawings 11715-CBM-096B, Sheets 1 of 4, 2 of 4 and 3 of 4, between the sets of valves listed below.
VALVES LINE MOV-1865A and 1-SI-125 12"-SI-123-1502 1-SI-123 and 1-SI-125 3/4"-SI-78-1502 MOV-1865B and 1-SI-142 12"-SI-124-1502 1-SI-140 and 1-SI-142 3/4"-SI-84-1502 MOV-1865C and 1-SI-159 12"-SI-125-1502 1-SI-157 and 1-SI-159 3/4"-SI-80-1502 Class
2 II.
IMPRACTICAL CODE REQUIREMENTS Class 2 System Hydrostatic Test per IWC-5222.
P =2485 psig.
f-g d
T=200*F, Test pressure per the code is 2733.5 psig since there is no overpressure protection for the~above components.
III. BASIS FOR REQUEST Check ' valves 1-SI-125, 1-SI-142, and 1-SI-159 at the Class 1 and 2 system boundaries prevent the pressurization of the above-components without pressurizing the primary system. The required test pressure is 2733.5 psig as stated above, which would overpressurize the primary system.
IV.
ALTERNATE TESTING As an alternative, it is_ requested that the Class 2 components listed above be tested to the conditions of IWB-5222 which is required for the adjacent Class 1 piping. The nominal operating pressure is 660 psig and temperature is 120*F.
Thus, testing per IWB-5222 would require a test pressure of 724 psig. This should be.
adequate considering the nominal operating conditions.
OV N1-004d/68 4-28 Rev. O March 6, 1988
RELIEF REQUEST SPT n I.
IDENTIFICATION OF COMPONENTS System
Main Steam (Steam) Decay Heat Release Feedwater Chemical Feed Blowdown Sampling Components: Secondary side of the Steam Generator and piping located on drawings 11715-CBM-070B, Sheet 1 of 3, 2 of 3,
and 3 of 3; 11715-CBM-074A, Sheet 1 of 3;
11715-CBM-089B, Sheet 3 of 4; 11715-CBM-098A, Sheet 2 of 5; and 11715-CBM-102A, Sheet 2. of 2; between the valves listed in Table SPT-11.
Class
2 II.
IMPRACTICAL CODE REQUIREMENTS Class 2 Hydrostatic Test per IWC-5222 and IWA-5213(d).
For Feedwater components, P =1100 psig, T,>200*F, test pressure per g
IWC-5222 would be 1375 psig.
For Yhe Chemical Feed components, P =1775 psig, T <200*F, test pressure per IWC-5222 would be 1952.5 d
d psig.
The remaining components have P =1085 psig, T 200'F, test s
d d
pressure per IWC-5222 would be 1356 psig III. BASIS FOR REQUEST Westinghouse, the manufacturer of the steam generators, gives specific testing requirements for the steam generator which must also be applied to the components listed above because these components cannot be isolated from the steam generators.
IV.
ALTERNATE TESTING The Westinghouse Technical Manual for the Steam Generator requires the secondary side to be pressurized to 1356 psig, held for 30 minutes and then reduced to design pressure (1085 psig) for a sufficient time to permit proper examination of welds, closures and surfaces for leakage or weeping.
The secondary side will be held at 1356 psig for 30 minutes and then at 1085 psig for a minimum of 3 1/2 hours in accordance with the Code.
A VT-2 examination will then be performed.
O V
N1-004d/68 4-29 Rev. O March 6, 1988 v
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Table SPT-ll Components COMPONENT CONNECTED PIPING COMPONENT 1-RC-E-1A 32"-SHP-1-601 SV-MS-101A to 32"-SHP-22-601 SV-MS-102A SV-MS-103A SV-MS-104A SV-MS-105A to 6"-SHP-37-601/
1"-SHP-84-601 PCV-MS-101A to 3"-SHP-64-601 1-MS-327 1-MS-18' to 1 1/2"-SHPD-6-601 1-MS-22 to 1/2"-SHPD-71-601 1-MS-26 1-RC-E-1A 32"-SHP-1-601 1-MS-35 NRV-MS-101A 3"-SHP-60-601 1-MS-344 1-RC-E-1A 32"-SHP-1-601 to 3"-SHP-45-601 1-MS-344 to 3"-SHP-531-601 NRV-MS-103A to 1"-SHP-518-601 1-MS-346 1-MS-348 1
1-RC-E-1A 2"-SS-302-601 1-SS-576 1-RC-E-1A 32"-SHP-1-601 to 32"-SHP-22-601 to 3"-SDHV-1-601 to 4"-SDHV-4-601 HCV-MS-104 1-RC-E-1A 16"-WFPD-24-601 1-FW-47 to 3"-WAPD-27-601 1-W-68 to 3/4"-CFPD-1-601 1-WT-39 1-RC-E-1A 2"-WGCB-4-601 1-BD-1 2"-WGCB-5-601 1-BD-4 1"-WGCB-6-601 1-BD-2 J
N1-004d/68 4-30 Rev. 0
)
March 6, 1988
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RELIEF REQUEST SPT-11 (Cont.)
Table SPT-11 (Cont.)
Components COMPONENT -
CONNECTED PIPING COMPONENT 1-RC-E-1B 32"-SHP-2-601 to.32"-SHP-23-601 SV-MS-101B SV-MS-102B SV-MS-103B SV-MS-1043
-SV-MS-105B to 6"-SHP-38-601/
1"-SHP-85-601 PCV-MS-101B to 3"-SHP-65-601 1-MS-325 1-MS-57 to 1 1/2"-SHPD-8-601 1-MS-60 to 1/2"-SHPD-73-601 1-MS-64 1-RC-E-1B 32"-SHP-2-601 1-MS-74 NRV-MS-101B 3"-SHP-61-601 1-MS-353 1-RC-E-1B 32"-SHP-2-601 to 3"-SHP-61-601 to 3"-SHP-46-601 1-MS-353 to 3"-SHP-533-601 NRV-h"~103B to 1"-S'1P-520-601 1-MS-nv O
1-MS-357 1-RC-E-1B 2"-SS-225-601 1-SS-218 1-RC-E-1B 32"-SHP-2-601 to 32"-SHP-23-601 to 3"-bDHV-2-601 to 4"-SDHV-2-601 HCV-MS-104 1-RC-E-1B 16"-WFPD-23-601 1-FW-79 to 3"-WAPD-28-601 1-FW-100 to 3/4"-CFPD-2-601 1-WT-51 1-RC-E-1B 2"-WGCB-7-601 1-BD-10 2"-WGCB-8-601 1-BD-13 1"-WGCB-9-601 1-BD-11 4
Rev. O N1-004d/68 4-31
+
March 6 1988
___.___,__._____,___,r
RELIEF REQUEST SPT-11 (Cont.)
Table SPT-11 (Cont.)
O Components COMPONENT CONNECTED PIPING COMPONENT 1-RC-E-1C 32"-SHP-3-601 to 32"-SHP-24-601 SV-MS-1010 SV-MS-102C SV-MS-103C-SV-MS-104C SV-MS-105C to 6"-SHP-39-601/
1"-SHP-86-601 PCV-MS-101C to 3"-SHP-66-601 1-MS-95 1-MS-323 to 1 1/2"-SHPD-7-601' 1-MS-98~
to 1/2"-SHPD-75-601 1-MS-412 s
1-RC-E-1C 32"-SHP-3-601 1-MS-112 NRV-MS-101C 3"-SHP-62-601 1-MS-362 1-RC-E-1C 32"-SHP-3-601 to 3"-SHP-62-601 to 3"-SHP-47-601 1-MS-362 to 3"-SHP-532-601 NRV-MS-103C to 1"-SHP-519-601 1-MS-365 1-MS-336 1-RC-E-1C 2"-SS-227-601 1-SS-217 1-RC-E-1C 32"-ShP-3-601 to 32"-SHP-24-601 to 3"-SDHV-3-601 to 4"-SDHV-4-601 HCV-MS-104 1-RC-E-1C 16"-WFPD-22-601 1-W-111 to 3"-WAPD-29-601 1-W-132 to 3/4"-CFPD-3-601 1-WT-67 1-RC-E-1B 2"-WGCB-10-601 1-BD-19 2"-WGCB-11-601 1-BD-22 1"-WGCB-12-601 1-BD-20 l
O V
N1-004d/68 4-32 Rev. 0 March 6, 1988
RELIEF REQUEST SPT-12 p
I.
IDENTIFICATION OF COMPONENTS
' Component Cooling, Chemical and Volume Control, Fuel System Pit
Cooling, Safety Inj ection,
Quench
Spray, Recirculation Spray, Service Water and Sampling Components: All piping and components included in the system hydrostatic test boundaries Class 1, 2 and 3 II.
IMPRACTICAL CODE REQUIREMENTS Per IWA-5265(b)..."the imposed pressure on any component, including static head, will not exceed 106% of the specified test pressure for the system."
III. BASIS FOR RELIEF Portions of the above systems not capable of being isolated within the system hydrostatic test boundary are located throughout the plant. Certain non-isolatable portions of the above systems have variations in elevation within the boundaries that would result in imposed pressures in excess of six percent of the specified test r~s pressure.
It is Virginia Electric and Power Company's desire to g
}
limit the test pressure imposed on system components to 106% of the s'
specified test pressure (as required by paragraph IWA-5265(b)).
Thus, due to the effects of static head, portions of the piping at higher elevations will be subjected to a test pressure lower than that specified. There is no practical ~ method for isolating the piping segments to achieve the required test pressure at all elevations.
IV.
ALTERNATE-TESTING Hydrostatic testing of systems that cannot be isolated to meet the system test pressure at the test soundary high point and the 106%
system test pressure maximum at the test boundary low point shall be conducted by pressurizing to the system test pressure at the low point in the test boundary.
Note: In a Safety Evaluation Report on Duane Arnold Energy Center (Docket No.
50-331) dated 03/31/86, relief was granted from IWA-5265(b) for situations as described above.
1 t
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i N1-004d/68 4-33 Rev. O Match 6, 1988 i
=.
RELIEF REQUEST SPT-13 O
I.
IDENTIFICATION OF COMPONENTS System
Reactor Coolant Components: Primary and Secondary side of the Steam Generators located on drawings 11715-CBM-070B and 11715-CBM-093A, Sheet 1 of 3, 2 of 3, and 3 of 3.
Class
1 and 2 II.
IMPRACTICAL CODE REQUIREMENTS System Leakage Test. IWB-5221; System Hydrostatic Test, IWB-5222; Visual Examination, IWA-5240 III. PASIS FOR RELIEF Primary to secondary leakage eurveillance detection using Code described visual detection techniques would be limited in usefulness and hazardous to conduct.
IV.
ALTERNATE TESTING O'
The normal primary to secondary leakage surveillance requirements of North Anna's Technical Specifications provide the necessary intended Code examination requirements for leakage detection.
O N1-004d/68 4-34 Rev. O March 6, 1988
g NORTH AhMA tl NIT 1 151 CLASS!FICATION BOJNDARY ORAWINGS CRAWING SHEET ORAWING CLASS CLASS CLASS NUM8ER NUMBER TITLE 1
2 3
11715 C88 006A 1073 AIR COOLING & PURGING SYSTEM 2
11715 C881028 10F1 INTERIOR FIRE PROTECT!0N & MOSE RACIC SYS 2
11715 CBM 070A 10F3 MAIN STEAM SYSTEM 3
)
30F3 MAIN STEAM SYSTEM 3
11715 CEM 0708 1073 MAIN STEAM SYSTEM 2
3 20F3 MAIN STEAM SYSTEM 2
3 3073 MAIN STEAM SYSTEM 2
3 11715 CBM 072A 20F3 AUXILIARY STEAM & AIR REMOVAL SYSTEM 2
11715 CBM 074A 10F3 FEEDWATER SYSTEM 2
3 30F3 FEE 0 WATER SYSTEM 3
11715 CBM 078A 10F4 SERVICE WATER SYSTEM 3
30F4 SERVICE WATER SYSTEM 3
1 4074 SERVICE WATER SYSTEM 3
11715 CBM 0788 10F4 SERVICE WATER SYSTEM 2
3 20F4 SERVICE WATER SYSTEM 3
11715 C8M 078C 10F2 SERVICE WATER SYSTEM 3
20F2 SERVICE WATER SYSTEM 3
11715 CBM 078G 1072 SERVICE WATER SYSTEM 3
20F2 SERVICE WATER SYSTEM 3
11715 CBM 079A 10F3 COMPONENT COOLING WATER SYSTEM 3
20F3 COMPONENT COOLING WATER SYSTEM 3
3073 COMPONENT COOLING WATER SYSTEM 3
11715 C8M 079s 10F5 CCMPONENT COOLING WATER SYSTEM 2
3 20F5 CCMPONENT COOLING WATER SYSTEM 2
3 30F5 CCMPOWENT COOLING WATER SYSTEM 2
3 4075 CCMPONENT COOLING WATER SYSTEM 2
3 50F5 CCMPONENT COOLING WATER SYSTEM 3
i 11715 CsM 079C 1075 CCMPONENT C00 LING WATER SYSTEM 3
30F5 COMPONENT COOLING WATER SYSTEM 3
4075 CCMPONENT COOLING WATER SYSTEM 3
50F5 CCMPONENT COOLING WATER SYSTEM 3
11715 C8M 0790 40F8 CCMPONENT COOLING WATER SYSTEM 2
11715 C8M 082A 10F3 COMPRESSED AIR SYSTEM 2
vi Rev. O March 6, 1988 l
i 1
NCRTM AhkA UNIT 1 151 CLASS!FICAf!CN BOUNCARY CRAWINGS CRAWING SHEET ORAWING CLASS CLASS CLASS kUMBER NUMBER f!TLE 1
2 3
11715 C8M 032C 10F2 COMPRESSED AIR SYSTEM 2
l 11715 CBM 0827 10F1 CCMPRESSED AIR SYSTEM 2
11715 CBM 0824 10F3 COMPRESSED AIR SYSTEM 2
3073 COMPRESSED AIR SYSTEM 2
11715 CBM 088A 10F4 FUEL PIT CLEANING & REFUELING PURIF SYS 2
3 20F4 FUEL PIT CLEANING & 2EFUELING PURIF SYS 2
40F4 FUEL PIT CLEANING & REFUEL!kG PURIF SYS 3
11715 CBM 0899 30F4 SAMPLING SYSTEM 2
11715 CBM 0890 1071 SAMPLING SYSTEM i
2 11715 CBM 090A 10F2 VENT & CRAIM SYSTEM 2
l 11715 CBM 090C 10F3 VENT & CRAIN SYSTEM 2
30F3 VENT & CRAlW SYSTEM i
2 11715 C8M 091A 10F4 CONT QUENCH & RECIRC SPRAY SUS SYS 2
3 20F4 CONT QUENCM & REClRC $ PRAY SUS SYS 2
1 30F4 CONT QUENCH & RECIRC SPRAY SUS SYS 2
40F4 CONT QUENCH & RECIRC $ PRAY SUI SYS 2
11715 CBM 0918 10F1 CONT QUENCH & RECIRC SPRAY SUB SYS 2
3 11715 C8M 092A 1072 LEAKAGE Moulfot SYSTEM 2
20F2 CONTAINMENT VACULM SYSTEM 2
11715 CBM 093A 10F3 REACTOR COOLANT SYSTEM LOOP 1 1
20F3 REACf04 COOLANT SYSTEM LOOP 2 1
30F3 REACTOR COOLANT SYSTEM Loop 3 1
11715 C8M 0935 1073 REACTOR COOLANT SvsTEM 1
20F3 REACTOR COOLANT SYSTEM 2
11715 CSM 094A 1072 RESIDUAL HEAT REMOVAL SYSTEM 1
2 20F2 RESIDUAL NEAT REMOVAL SYSTEM 1
2 3
11715 C8M 0954 10F4 CHEMICAL ANO VOLUME CONTROL SYSTEM 3
20F4 CHEMICAL AND VOLUME CONTROL SYSTEM 3
3074 CHEMICAL AND voltME CONTROL SYSTEM 2
40F4 CHEMICAL AND VOLLME CONTROL SYSTEM 2
11715 C8M 0958 1072 CNEMICAL AND VOLUME CONTROL SYSTEM 2
3 20F2 CHEMICAL AND VOLUME CONTROL SYSTEM 2
vii Rev. O March 6, 1988 i
D NCRTH ANNA UNIT 1 IS! CLAS$lFICAf!CN BOUNOARY CRAWINCS CRAWING SHEET ORAWING CLASS CLASS CLASS kUMBER NUMBER TlfLE 1
2 3
11715 CBM 095C 1072 CHEMICAL AND VOLUME CCNTROL SYSTEM 1
2 2CF2 CHEMICAL AND VOLUME CCNTROL SYSTEM 1
2 11715 C8M 096A 1C73 SAFETY INJECTION SYSTEM 2
2CF3 SAFETY INJECTICN SYSTEM 2
3 3073 SAFETY INJECTICN SYSTEM 2
3 11715 CSM 0968 10F4 SAFEff !NJECTICN SYSTEM 1
2 2CF4 SAFETY INJECTION SYSTEM 1
2 30F4 SAFETY INJECTION SYSTEM 1
2 4074 SAFETY INJECT!CN SYSTEM 1
2 11715 CBM 098A 20F5 STEAM CENERATOR BLOWOOWN bYSTEM 2
30F5 STEAM CENERATOR BLOWDOWN SYSTEM 2
40F5 STEAM CENERATOR BLOWOOWN SYSTEM 2
11715 C8M 102A 20F2 CHEMICAL FEED SYSTEMS 2
11715 CBM 1058 1072 SECONDARY PLANT GAS SUPPLY SYSTEM 3
11715 CSM 10$C 1071 MISCELLANEOUS CAS SUPPLY SYSTEM 2
11715 C8M 06A 11F4 CONTAINMENT ATMCSPHERE CLEANUP SYS 2
2C'4 CONTA!nMENT ATMOSPMERE CLEAWup SYS 2
30F4 CONTAINMENT ATMOSPHERE CLEAWUP SYS 2
40F4 CONTAINMENT ATMOSPNERE CLEANUP SYS 2
11715 CBM L&S 2 1071 LEGEN05 & SYM60LS 11715 FB 0400 1071 AIR COMolfl0NING COM0ENSER WATER SYSTEMS 3
11715 FM 022J 10F1 SERVICE WATER SYSTEM RESERVOIR SPRAY 3
l 11715 FM 022K 10F1 SERVICE WATER SYSTEM RESERVOIR SPRAY 3
11715 FM 078W 1071 SERVICE WATER SYSTEM 3
13075 CBM 093C 10F2 REACf0R C00LAuf SYSTEM 1
2072 REACTOR COOLANT SYSTEM 1
13075 CBM 102C 1071 CHEMICAL FEED SYSTEM 2
viii Rev. O l
March 6, 1988
. ~.
OVERSIZE DOCUMENT PAGE PULLED SEE APERTURE CARDS NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS i
APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH,TIDC FTS 492-8989 E
- - = - -
--,---,y y-.. - -,,,
,___ _, _,_ _.

ML20197F126: Difference between revisions

Latest revision as of 13:11, 10 December 2024

Contents

Text

1.0 INTRODUCTION

4.1 INTRODUCTION

4.1 INTRODUCTION

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ML20197F126: Difference between revisions

Latest revision as of 13:11, 10 December 2024

Text

1.0 INTRODUCTION

4.1 INTRODUCTION

4.1 INTRODUCTION

Navigation menu

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