ML18038B885

Rev 8 to Surveillance Instruction 2-SI-4.6.G, ISI Program Unit 2

ML18038B885
Person / Time
Site:	Browns Ferry
Issue date:	08/14/1996
From:	TENNESSEE VALLEY AUTHORITY
To:
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ML18038B884	List: ML18038B883 ML18038B885
References
2-SI-4.6.G, NUDOCS 9706060122
Download: ML18038B885 (154)

Text

TENNESSEE VALLEYAUTHORITY BROWNS FERRY NUCLEARPLANT SURVEILLANCEINSTRUCTION 2-SI-4.6.G INSERVICE INSPECTION PROGRAM UNIT2 REVISION 8 PREPARED BY: J. LEWIS PHONE: 4866 RESPONSIBLE ORGAMZATION: NUCLEARENGINEERING APPROVED BY: EUGENE PRESTON, JR.

DA'IE:07/24/96 H'FECTIVEDATE'8/14/96 LEVELOF USE: CONTINUOUS USE VALIDATIONDA'IR NOT REQUIRED QUALITY-RELATED I 1 970sosoaa2 970soz (7 PDR ADOCK 05000260 PDRQ 0526193867 SFNP SI 2-SX-4.6,8 081496 8

REVISION LOG Revision Number:

8 Pages Affected: 19, 20, 21, 27, and 53 Description of Change:

IC ENHANCEMENT - This revision deletes the use of Inspection

Reports, incorporates NOIs, and references SIL-289 enhanced visuals.

REV 0008 TABLE OF CONTENTS 2-SI-4.6oG Page 1

Owner's Statement...

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1.0 INTRODUCTION

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1.1 1.2 1.3 Purpose o

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3. 0 PRECAUTIONS AND LIMITATIONS.

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13 5.0 SPECIAL TOOLS AND E{}UIPMENT...............................

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7.3 7.4 7.5 7.6 7.7 7.8 7.9 7.10 7.11 7.12 7.13 Responsibilities.................

Implementation...................

Components Sub)ect to Examination Calibration Standards............

Records and Reports Requests for Relief (RFR)

Corrective Action Program........

Repairs and Replacements.........

System Prcssure Tests

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Pump and Valve Inservice Testing.

Snubber Inservice Testing........

Augmented Examinations...........

Voluntary Examinations

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8.4 Examination Schedules..................

Lists of Stainless Steel and Dissimilar Metal Welds )~4" Diameter..............

Class 1 Valve List o

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REV 0008 OWNER'S STATEMENT 2-SZ-4 '.G Page 2

Owner:

Tennessee Valley Authority Address of'Corporate Office:

Chattanooga Office Complex 1101 Market Street Chattanooga, TN 37402-2801 Name a Address of Power Plant:

Browns Ferry Nuclear Plant P.O.

Box 2000 Decatur, AL 35609 Applicable Nuclear Power Unit:

Commercial Operation Date:

BFN, Unit 2 March 1, 1975 Construction Permit was issued prior to January 1,

1971.

RWVh2SI46G

1. 0 INTRODUCTION REV 0008 2-SZ-4.6.G Page 3

~PII 058 This Znservice Inspection (ISI) Program is an administrative Surveillance Instruction (SZ) employed to obtain data through nondestructive examinations (NDE) of ASME Section XZ Code Class 1,

2, and 3 equivalent components that can be used to determine if a flaw is an isolated case or is of a generic nature. It shall serve as TVA's ZSI plan and schedule in accordance with the requirements of IWA-1400. The examinations required by this program shall establish acceptance for continued use of components during operation.

This program is organized to comply with the ZSZ NDE requirements of the 1986 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code/

Section XI, Division 1, Articles 1000,

2000, 3000, and 6000 in accordance with Title 10 Code of Federal Regulations (CFR) Part 50, 50.55a(g);

to implement the Browns Ferry Nuclear Plant (BFN) Technical Speci fications, Unit 2, Surveillance Requirement 4.6.G.;

and to fulfillthe zequizements of SSP-6.10, ASME Section XI Inservice Inspection Program.

This ISI Program reflects the built-in limitations of the original plant design,

geometry, construction, component materials, and state-of-the-azt nondestructive examination techniques. It specifies the number of components to be

examined, the examination methods to be used and provides schedule tables from which specific items are scheduled for examination by Mechanical/Nuclear (M/N) Engineering.

These items are documented in scan plans for each refueling outage.

1.2 Sco e

(

licabilit )

This program outlines details for planning and performing the second inspection interval NDE foz the ASME Section XI Code Class 1, 2, and 3 equivalent components at BFN in accordance with IWA-2432, Inspection Program B.

The ASME Section XI Code Class Boundary Drawings and the ZSI Drawings listed in Section 2.5 identify the components and systems to be examined.

These drawings aze prepared and maintained by M/N Engineering and aze issued and controlled through BFN Records Management (RM).

R:RWQSI46G

REV 0008 2-SZ-4.6.G Page 4

Personnel responsible for performance of the examinations should familiarize themselves with the requirements of this program prior to performing the examinations.

Specifics concerning performance of NDE aze not a part of this program, but are included in ZEP-100, Nondestructive Examination Procedures.

Elements of ASME Section XI, Articles 4000,

5000, 6000, and 7000 other than NDE, such as Pump and Valve Znservice Testing/

Snubber Znservice Testing, Repairs and Replacements, and System Pressure

Tests, are covered by other procedures.

See Sections 7.8, 7.9, 7.10, and 7.11.

1.3

~Fze u~enc 1.3.1 Zns ection Interval and Zns ection Periods The ISZ examinations required by ASME Section XZ, Division 1, IWA-2432, Inspection Program B shall be performed during this inspection interval (May 24/

1992 to May 24, 2001).

The inspection interval duration is nine years since the first interval was extended by one year per IWA-2400(a),

1974 Edition/Summer 1975 Addenda (See IWA-2430(d), 1986 Edition for equivalent rule).

The inspection interval shall be separated into three inspection periods of three years each.

Except for examinations that may be deferred to the end of the inspection interval, the required examinations shall be performed in accordance with the, following schedule that complies with IWB-2412, Program B and Table ZWB-2412-1s IWC-2412, Program B and Table ZWC-2412-1; ZWD-2412, Program B

and Table IWD-2412-1; and (N-491)-2410(b) and (c) and Table -2410-2, Program B.

Inspection Period Minimum Exand.nations Co leted Maximum Examinations Co

leted, 8

First (5/92-5/95)

Second (5/95-5/98)

Third (5/98-5/01) 16 50 100 34 67 100 The examinations deferred to the end of the inspection interval shall be completed before the end of the inspection interval.

The inspection interval may be extended in accordance with IWA-2430(e) if unit 2 is out of service continuously for six months oz more.

R WVh2SI46G

REV 0008 2-SZ-4.6 '

Page 5

2.1 Technical S ecifications BFH Unit 2 Technical Specifications, Surveillance Requirement 3/4.6.G, Structural Integrity.

2.2 Final Safet Anal sis Re ort Browns Ferry Nuclear Plant Updated Final Safety Analysis

Report, Volume 2, Section 4.12.

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NRC Documents 10 CFR Part 50, 50.55a(g).

10 CFR Part 50.2.

Regulatory Guide 1.26.

Regulatory Guide 1.147.

ZE Bulletin 80-13, Core Spray Spargers.

Generic Letter 88-01, NRC Position on ZGSCC in BWR Austenitic Stainless Steel Piping.

NUREG-0313, Rev.

2, Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping, Final Report.

NUREG-0619, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle cracking.

2.4 Plant Procedures and Instructions SSP-3.1, Quality Assurance Program.

SSP-3.4, Corrective Action.

SSP-4.5, Regulatory Reporting Requirements.

SSP-6.9, ASME Section XI Repairs and Replacements.

SSP-6.10 SSP-8.5, ASME Section XI Znservice Inspection.

ASME Section XI System Pressure Test Program.

SSP-8.6, ASME Section XI Pump and Valve Inservice Testing.

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REV 0008 2-SZ-4

~ 6 ~ G Page 6

2.0 REFERENCES

(Continued) 2-SI-4.6.H.1, Visual Examination of Hydraulic and Mechanical Snubbers.

MCI-0-001-VLV001, Main Steam Isolation Valves Atwood Morrill Co. Disassembly, Znspection,

Rework, and Reassembly.

MCZ-0-001-VLV002, Main Steam Relief Valves Target Rock Model 7567 Disassembly, Inspection,

Rework, and Reassembly.

MSI-0-001-VSL001, Reactor Vessel Disassembly and Reassembly.

MCZ-0-068-PMP001, Maintenance of Reactor Water Recirculation Pumps' MMI-46, Liquid Penetrant Examination of Piping and Piping Components Which Were Exposed to Residue from Plant Fire Unit 1 and 2.

MMI-53, Evaluation of Corrosion Damage of Piping Components Which Were Exposed to Residue from March 22, 1975 Fire (canceled).

MSI-0-001-INS001, Reactor Vessel Internals Visual and Ultrasonic Inspection.

ZEP-200, Qualification and Certification Requirements for NQA NDE Personnel.

ZEP-100, Nondestructive Examination Procedures Approved for use on CSSC Items at all Nuclear Plants.

2.5.1 Unit 2 Section XI Code Class Boundary Drawings 2-47E2600-57A-ZSI, RCS Instrumentation.

2-47E600-58-ISI, Mech. Instr.

and Controls.

2-47E610-43-1-ZSI, Mech. Control Diag. Sampling and Water Quality.

2-47E2600-301-ISI, CRD Hyd. Sys.

2-47E2600-302-ZSZ, CRD Hyd. Sys.

2-47E600-599-ISI, Mech.

ICC.

R:WVA2SI46G

2. 0 REFERENCES

{Continued)

REV 0008 2-SZ-4.6.G Page 7

0-117C2556-4-ISI, Rack 25-18.

0-117C2556-5-ISI, Rack 25-18.

2-164C5981-4-ZSI, Rack 25-7.

2-164C5981-S-ISI, Rack 25-7.

2-164C5984-4-ISI, Rack 25-56A.

2-164C5984-5-ISI, Rack 25-56B.

2-164C5985-4-ISI, Rack 25-57.

2-47E801-1-ISZ, Main Steam.

2-47E801-2-ISZ; Main steam.

.2-47E803-1-ZSI, Feedwater.

2-47E803-S-ISI, Feedwater.

2-47E807-2-ISZ, Turbine Drains 4 Misc Piping.

2-47E810-1-ISZ, Reactor Water Cleanup.

2-47E811-1-ISZ, Residual Heat Removal.

2-47E812-1-ISZ, High Pressure Coolant In5ection.

2-47E813-1-ISZ, Reactor Coze Isolation Cooling.

2-47E814-1-ZSZ, Core Spray.

2-47E815-4-ISZ, Aux. Boiler Sys.

2-47E817-1-ISZ, Nuclear Boiler.

2-47E820-2-ISZ, Control Rod Drive Hydraulic.

2-47E2820-6-ZSZ, Control Rod Drive Hydraulic.

0-47E839-5-ZSZ, Hypochlorite System.

2-47E822-1-ZSZ, Reactor Bldg Closed Cooling Water.

2-47E844-2-ISI, Raw Cooling Water.

2-47E852-1-ZSZ, Floor and Dirty Radwaste Drainage.

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REV 0008 2-SZ-4.6.G Page 8

2-47E852-2-IS:,

Clean Radwaste 4 Decon Drainage.

2-47E854-1-ZSZ, Standby Liquid Control.

2-47E855-1-ISZ, Fuel Pool Cooling.

2-47E856-2-ISI, Demineralized Water.

2-47E858-1-ISI, RHR Service Water.

2-47E859-1-ISZ, Emergency Equipment Cooling Mater.

2-47E867-3-ISI, Sampling and Mater Quality.

Unit 0 ZSI Component Support Drawing ZSZ-0368-C, EECW and RHRSM Pumping Station Class 3.

ISI-0390-C, EECW Unit 3 Class 3.

ZSI-0391-C, Raw Cooling Water Unit 1 Class 3.

Unit 2 ZSI Bolting, Nozzles, and Maids Drawings CHN-2046-C, Reactor Vessel Nozzle and Weld Locations Class l.

ISX-0444-C, Reactor Vessel Bottom Head Assy. Class 1.

ZSI-0316-A, Reactor Vessel Clad Patches.

ZSI-0343>>A, Core Differential Pressure and Liquid Control Nozzle Weld Locations.

ISX-0351-A, Instrumentation Nozzles Class 1.

ZSX 0312 bg )Cain Steam bolting Class 1

".ISX-0347 b, Recirculation Inlet Nozzles Class 1.

IIISI-0031-C, Reactor building Closed Cooling Water Syst~ Class 2 Welds.

~i"

~ sf>>

ISX-0040-C, CRD Hydraulic Header Class 2 Maids.

ZSI-0103-C, Core Spray System Class 2 Maids.

ISZ-'0128-C, HPCZ System Class 2 Maids.

2.0 REFERENCES

{Continued)

REV 0008 2-SZ-4 '.G Page 9

ISI-0129-C, RCIC System Class 2 Welds.

ISI-0221-C, RHR System Class 1 Welds.

ISI-0222-C, Main Steam System Class 1 Weld'.

ISZ-0266-C, Vessel Stud Locations Class l.

ISI-0269"C, Feedwater System Class 1 Welds.

ISI-0270-C Recirculation System Class 1 Welds.

ISI-0271-C, Core Spray System Class 1 Welds.

ISI-0272-C,

RWCU, RCIC, and CRD Systems Class 1 Welds.

ISI-0273-C, HPCZ System Class 1 Welds.

ZSI-0292-C, Control Rod Drive Penetrations, Drain

Nozzle, and Flux Monitor Nozzles Class 1.

CHM-1090-A, RPV Control Rod Drive Penetration, BFN.

CHM-1091-A, RPV Support Shirt Weld, BEN.

CHM-1094-A, RPV Nozzle to Vessel Wells, BFN.

CHM-1095-A, RPV Vessel and Head Wells, BFN.

ZSI-0380-C, Standby Licpd.d Control System Class 1 Welds.

ZSI-0383-C, Feedwater Instrumentation Class 1 Welds.

ZSI-0406-C, RHR Heat Exchanger Welds and Supports Class 2.

ISI-0407-C, Recirculation Pump Bolting Class 1.

ISI-0408-C, Closure Head Assembly Class 1.

ISI-0410-C, Jet Pump Znstrument Nozzle Class 1.

MSG-0018-C, RHR System Class 2 Welds.

MSG-0021-C, Main Steam Class 2 Welds.

2.0 REFERENCES

(Continued)

REV 0008 2-SI-4 '.G Page 10-2.5.4 Unit 2 ZSI Component Support Drawings ISI-0310-B, RHR Pump Class 2.

ISI-0032-C, Reactor Building Closed Cooling Water System Class 2.

ZSI-0041-C, CRD Header Class 2.

ISI-0079-C, Main Steam System Class 2.

ISZ-0105-C, Core Spray System Class 2.

ISI-0130-C, HPCI System Class 2.

ISI-0131-C, RCZC System Class 2.

ISI-0133-C, FPC System Class 3.

ISI-0145-C, RHR Service Water System Class 3.

ISZ-0274-C,

RWCU, RCIC, and CRD Systems Class 1.

ZSZ-0275-C, HPCI System Class 1.

ISI-0276-C, RHR System Class l.

ISZ-0277-C, Feedwater System 'Class 1.

ISZ-0278-C, Recirculation System Class l.

ZSI-0279-C, Main Steam System Class 1.

ZSI-0280-C, Coze Spray System Class 1.

ZSZ-0324-C, RHR System Class 2.

ISZ-0379-C, Standby Liquid Control System Class 1.

ISI-0387-C, Feedwater Instrumentation Class 1.

ZSI-0412-C, Main Steam Relief Valve Blowdown Class 3.

ISZ-0415-C, Reactor Vessel Class 1.

R:RVh2S146G

REV 0008 2-SI-4.6.G Page 11 2

6 Interface Documents 2.6.1 BFN-VTM-B014-0010, BEW Reactor Pressure Vessel Manual, Contract 66C60-90744.

2. 6.2 BFN-VTM-B580-0010, BfJ Recirculation Pump Manual, Contract 67C60-91750.

2. 6.3 BFN-VTM-B260-0030, Bingham Pump Co.

RHR Pump Manual, Contract 66C60-90744.

2.6.4 BFN-VTM-P160-0010, Vendor Technical Manual For Pzefex Corp.

Heat Exchangers Types

NEN, CEU,

CES, and

CEN, Contract 66C60-90744.

2.7 Reference Documents ASME Boiler and Pressure Vessel

Code,Section XI, Division lg 1986 Edition.

ASME Section XI Code Cases as listed in Section 4.1.

2.8 General Electric Service Instruction Letters 2.8.1 2.8.2 2.8.3 2 ' '

2.8.5 2.8.6 2.8.7 2.8.8 2.8.9 2.8.10 2.8.11

2. 8. 12 GE SIL No. 289, Core Spray Piping Visual Examination.

GE SZL No. 409, Zncoze Dry Tube Cracks.

GE SZL No. 420, Inspections of Jet Pump Sensing Lines.

GE SZL No. 433, Shroud Head Bolt Cracks.

GE SZL No. 462, Shroud Support Access Hole Cover Cracks.

GE SZL No. 572, Coze Support Shroud Examination.

GE SZL No. 330, Jet Pump Beams Inspections.

GE SZL No. 465, Jet Pump Throat Inspections.

GE SIL No. 551, Jet Pump Riser Brace Inspections.

GE SZL No. 574, Jet Pump Adjusting Screws Inspections.

GE SZL No. 544, Visual Examination of RPV Top Guide.

GE SZL No. 571, Instrument Nozzle SAFE ENDS Examination.

2.8.13 GE SIL No. 588, Top Guide and Coze Plate and Bolting Examinination RWVh2SI46G

REV 0008 2-SI-4 '.G Page 12 2.9 Miscellaneous Documents 2.9.1 Incident Investigation No. 11-B-93-026 Unit ¹2 Steam Dryer Bracket Inspection.

2'.2 DNE Caclulcation, Exclusion Criteria for ISI Scope.

RIMS R14950829109.

R:WVh2Sl46G

REV 0008 2-SI-4 '.G Page 13 RADCON shall be contacted prior to any work in a radiologically controlled area (RCA).

RADCON shall determine the requirements foz a radiological work permit (RWP) and any other radiological requirements.

4.0 CODES OF RECORD AND CODE CASES 4.1 Current Code Re irements and Code Cases This program is in effect for unit 2 for the second inspection interval beginning on May 24, 1992.

The Units 1 and 3 program is contained in 1/3-SI-4. 6.G.

The Code of Record for the second inspection interval of unit 2 is the 1986 Edition of the ASME-Boiler and Pressure Vessel

Code,Section XI, Division 1 in accordance with 10 CFR SO/

50.55a(g) (4). Additionally, in accordance with 10 CFR 50, 50.55a(b) (2) (ii), the extent of examination for Examination Category B-J welds shall be in accordance with the 1974

Edition, Summer 1975 Addenda of ASME Section XI. Extent of examination is defined as the criteria for the selection of the Class 1 B-J welds to be examined.

See Section 7.3.2.B.

Beginning on December 15,

1995, NDE methods, qualification of personnel, weld reference

system, and standards foz examination evaluation shall be in accordance with the 1989 Edition of ASME Section XI as allowed by 10CFR50.55a(g)(4)(iv).

Certification of NDE personnel shall be in accordance with the 1984 Edition of ASNT SNT-TC-IA as approved by the Nuclear Regulatory Commission's (NRC's) letter from S.C. Black to O.

D.

Kingsley, Jz.,

dated January 18, 1990 (TAC No. 72833).

TVA shall use the following Code Cases that have been approved by the NRC per Regulatory Guide 1.147 or by special written permission from the NRC:

A.

Code Case N-307-1, Revised Ultrasonic Examination Volume for Class 1 Bolting, Table IWB-2500-1, Examination Category B-G-1, When the Exand.nations Aze Conducted From the Center-Drilled Hole,Section XI, Division 1.

B.

Code Case N-435-1, Alternative Examination Requirements for Vessels With Wall Thickness 2 in. or Less,Section XI, Division 1.

RWWQSI46G

REV 0008 2-SI-4 '.G Page 14 4.0 CODES OF RECORD AND CODE CASES (Continued)

C, Code Case N-445, Use of Later Editions of SNT-TC-1A for Qualification of Nondestructive Examination Personnel,Section XI, Division 1.

D.

Code Case N-457, Qualification Specimen Notch Location foz Ultrasonic Examination of Bolts and Studs,Section XI, Division l.

E.

Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1.

F.

Code Case N-461, Alternative Rules foz Piping Calibration Block Thickness,Section XI, Division l.

G.

Code Cas'e N-491, Alternative Rules for Examination of Class 1, 2, 3, and MC Component Supports of Light-Water Cooled Power Plants,Section XI, Division 1.

Use approved by the Nuclear Regulatory Commission' (NRC's) letter from Fzedrick J.

Hebdon to Dz. Mark O. Medford, dated May 18, 1992 (TAC Nos.

M81952, M81953, and M81954).

H.

Code Case N-524, Alternate Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping - Section XI, Division 1.

Use approved by the NRC's letter from Frederick J.

Hebdon to Oliver D. Kingsly, dated September 28, 1994.

4.2 Histor of Codes of Record and Code Cases For unit 2 a preservice inspection (PSI) program was not required.

TVA performed a self-imposed PSI program for Class 1

components to the 1971 Edition, Summer 1971 Addenda of ASME Section XI.

For unit 2 the history of the ASME Section XI code of record and Code Cases used are as follows:

A.

The first peziod of the first interval, in effect from March 1, 1975 through July 1,

1981, was to the 1971

Edition, Summer 1971 Addenda of ASME Section XI. The long duration on this period was due to an extension for the fire outage and an additional one year extension in accordance with IWA-2400 to establish concurrent intervals foz units 1, 2, and 3 beginning with the second period.

See NRC letter dated June 20, 1986 (A02 860630 006) for approval of these adjustments.

R:WWQS146G

REV 0008 2-SZ-4.6.G Page 15 4.0 CODES OF RECORD AND CODE CASES (Cr ntinued)

B.

The second period (July 1, 1981 through July 7, 1988) and the third period (February 26, 1986 through May 23, 1992) were to the 1974 Edition with Addenda through Summer 1975 of AsME section xI. Ultrasonic examination and evaluation of piping welds was upgraded to the 1977 Edition, Summer 1978 Addenda of ASME Section XZ for these periods.

This included examination per IWA-2232(b), IWA-2232(c), and Appendix IZI (to the extent specified in Request for Relief ZSZ-15) and evaluation per ZWA-3000, IWB-3000, and IWC-3000 of the 1977 Edition, Summer 1978 Addenda.

The overlap of the second and third periods occurred because of the extended outage from September 15, 1984 to May 24, 1991 and TVA's decision to complete the second and third period examinations during this time to close out the first interval. This decision was made since the first interval had been extended twice and it was prudent to end it and commence with a second inspection interval to a current Edition of ASME Section XI.

C.

Beginning January 1,

1992, the presezvice inspection of pipe welds, including the extent of examination, (Examination Categories B-F, B-J, and C-F) was performed in accordance with the 1977 Edition, Summer 1978 Addenda of ASME Section XI, ZWA-2232, IWA-3000, IWB-2200 (c), Table IWB-2500-1, and Table IWC-2500-1.

D.

Code Cases N-234'" 235'07-lg 308'41'56'16, 435-1g

460, and 461 that were approved by Regulatory Guide 1.147 were used at BFN during the first interval.

5.0 SPECIAL TOOLS AND EQUIPMENT Equipment shall be specified and controlled by individual NDE Procedures.

6 '

ACCEPTANCE STANDARDS The acceptance criteria shall be in accordance with the individual NDE Procedures of ZEP-100 that shall comply with the requirements of ASME Section XI, Articles IWA-3000, ZWB-3000, ZWC"3000, IWD-3000, and (N-491)-3000+

Evaluations of examinations in accordance with ZWB-3132.4, IWB-3142.4g IWC-3122. 4, ZWC-3132. 3, (N-491) -3112. 3, or (N-491) -3122. 1 shall be

REV 0008 2-SI-4 '.G Page 16 submitted to the regulatory authori y having jurisdiction at the plant site.

This information shall be submitted with the Znservice Inspection Summary Report or, if deemed necessary, a separate report shall be submitted.

7.0 INSTRUCTION STEPS/ELEMENTS Any revisions initiated by other groups shall be submitted to M/N Engineering for approval prior to incorporating the revisions into this program.

F 1 Res onsibilities 7.1

~ 1 Corporate Engineering, Materials 4 Inspection (M 6 I) responsibilities:

A.

Providing ISI and/or PSZ ASME Section XI interpretations as requested by various site organizations or as required in program development and implementation.

B.

Providing assessments and ovezsite of this program and ISI activities on site.

C.

Review and comment all PSZ/ZSI Program Requests for relief prior to issuance.

7'.2 M/N Engineering zesponsibilities:

A.

Defining ASME Section XI Code Class 1, 2, and 3

equivalent boundaries in accordance with 10 CFR 50.2, 10 CFR 50.55a, ASME Section XI, and Regulatory Guide 1.26, R3.

B.

Preparing/revising ASME Section XI Code Class Boundary Drawings to identify the ASME Section XZ Class 1, 2, and 3 equivalent boundaries within each plant system as defined in 7.1.2.A.

See Section 2.5 for drawing list.

C.

Preparing/revising ASME Section XZ ZSI drawings that identify the Class 1, 2, and 3 equivalent components (including supports) that require inservice and/or preservice nondestructive exand.nation (NDE) to comply with ASME Section XI requirements.

See Section 2.5 for drawing list.

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REV 0008 2-SI-4 '.G Page 17 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)

D.

Preparing/revising this instruction (ISI Program) and submitting it to:

(1)

RM for approval and issue as a controlled document.

(2)

RM for subsequent submittal to the ANII for a detailed review per IWA-2110(a) (1) and (a) (2).

See Sections 7.1.5.A and 7. 1.8.A.

(3)

Site Licensing for subsequent submittal to the NRC.

See Section 7.1.4.A.

E.

Ensuring that this program provides detailed instructions for ISI including the following information as a minimum:

(1)

The ASME Section XI Code of Record for ISI.

(2)

The inspection interval.

(3)

A list of the ASME Section XI Code Class Boundary drawings.

(4)

A list of the ASME Section XI ISI dzawings.

(S)

An examination schedule providing the total number of each Code Item Number, the number of samples foz the inspection interval, and the number of samples for each period of the interval.

(6)

The NDE method to be used for each Item Number.

(7)

The ASME Examination Category and Item Number for each component.

(8)

Copies of all Relief Requests.

(9)

Name and address of the Owner.

(10) Name and address of generating plant.

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REV 0008 2-SI-4

~ 6 ~ G Page 18

7. 0 INSTRUCTION STEPS/ELEMENTS (Continued)

J (ll) Name or number designation of the unit.

(12)

Commercial operation date of the unit.

(13)

A description of the system for maintaining status of completed examinations.

(14)

A discussion of scan plans that provide details of required component examinations, such as component identifier, NDE procedure, calibration standard reference, ISZ drawing

number, sheet number, etc.

(15)

Augmented examination requirements closely zelated to ASME Section XI based on other codes/standards, regulatory guides, NRC commitments, etc.

F.

Providing a list of components scheduled for examination during each refueling outage to Inspection Services Organization (ISO) foz scan plan development.

This list shall include the component identifier, ASME Section XI examination category and item number, examination method, ISI drawing number and sheet

number, and examination requirement source.

See Section 7.2.1.B.

G.

Approving the scan plan and revisions and submitting copies of the approved scan plan to site management and the ANZZ. See Section 7.2.1.B.

H.

Providing any additional samples required due to examinations performed.

See Section 7.2.2.

Z.

Notifying Site Engineering of an indication found during the final additional sample examination foz their evaluation.

See Sections 7.1.3.C and 7.2.2.B.(4).'.'WVh2S 146 G

REV 0008 2-SI-4

~ 6. G Page 19 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)

J.

Preparing a Request for Relief (RFR) when required because of areas that are inaccessible or partially inaccessible foz examination or because it is determined that conformance with Code requirements is impractical.

See Sections 7.1.5.D and 7.2.3.E for ZSO responsibilities of notifying M/N Engineering if limited exams indicate the need to initiate an RFR.

See Section 7.6.

K.

Submitting Requests for Relief to the Site Licensing organization.

See Section 7.6.

L.

Performing NDE per the requirements of this instruction.

See Section 7.2.3.

M.

Ensuring that ISI/PSZ examinations are performed in accordance with TVA NDE procedures or in accordance with contractor procedures that have been reviewed by ISO.

See Section 7.2.3.

N.

Administering AIA contract and ensuring that services of AIA aze used when performing Code required activiti.es.

TVA's interface with the Authorized Inspector foz ISI, repairs, and replacements is defined in SSP-6.9 and SSP-6.10.

O.

Providing AIA representative with access to plant and documentation in accordance with IWA-2130 of ASME Section XZ.

P.

Notifying ANII prior to performing examinations.

Q.

Preparing NOI's, documenting followup examinations, and assuring

closure, proper filing, and providing/coordinating dispositions for NOZ's in accordance with SSP-6.10 and SSP-3.4.

See Section 7.2.2.A.

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REV 0008 2-SI-4.6 '

Page 20

7. 0 INSTRUCTION STEPS/ELEMENTS (Continued)

R.

Preparing examination reports and recording them (report number,

date, examiner's initials and comments/NOI number) in the scan plan.

When insezvice examinations are implemented by" instructions other than this program (i.e. g MMZ s ) g copies of the examination data sheets shall be submitted to M/N Engineering by the performing organization.

These data sheets shall be used as examination reports and incorporated into the scan plan.

See Section 7.2.1.B.(3).

S.

Ensuring that all scan plan examinations aze complete prior to completion of an outage and that all examinations are recorded in the scan plan.

T.

Preparing inservice inspection summary reports, preparing augmented examination summary reports, obtaining ANII signature on NZS-1 form, coordinating summary report reviews with ZSO, and submitting inservice inspection and augmented examination summary reports to Site Licensing.

The NZS-1 summary report shall be submitted to Site Licensing within 60 days of the end of the outage.

See Section 7.S.

U.

Preparing and submitting the Site Final Report to RM as a

QA record.

See Sections 7.1.6.C, 7.S, and 7.12.4.

V.

Ensuring records used as PSI records from manufacturers, or construction organizations comply with procedures.

W.

Calculation of component support acceptance ranges, if required, in accozdance with ZEP-100, N-GP-7 and N-VT-1. See Section 7.3.6.D.

X.

Maintaining calibration blacks stored at the plant site.

See Section 7.4.

Y.

Initiating a pre-outage meeting on augmented examination per Section 7.12.

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REV 0008 2-SZ-4.6.G Page 21 7 '

ZHSTRVCTION STEPS/ELEMENTS (Continued) 7.1

~ 3 Site Engineering responsibilities:

A.

Designing, fabricating, erecting, and constructing components to quality standards commensurate with the safety function to be perfozmed.

This includes designing for access in accordance with ASME Section XI, IWA-1400(b) and ZWA-1500.

B.

Performing engineering evaluations in support of NOZs or other examination indications.

See Sections 7.2.2.A and 7.12.

C.

Performing evaluations of indications found during final additional sample examinations to determine if further action is required.

See Sections 7.1.2.I and 7.2.2.B.(4)

~

D.

Determining those component supports that could be affected by observed failure modes and could affect nonexempt components as prescribed in Section 7.2.2.B.(3).

~

E.

Providing specific written details for any augmented zequirements for which they are responsible per Section 7.12 and determining if a post examination meeting is required.

7.1.4 Site Licensing responsibilities:

Filing this Surveillance Instruction (2-SZ-4.6.G) and revisions with the NRC per IWA-1400(c). M/N Engineering should be included on distribution of correspondence.

See Section 7.1.2.D.(3).

B.

Submitting Requests foz Relief and Summary Reports to the NRC. M/N Engineering should be included on distribution of all related correspondence.

See Section 7.1.2.K, 7.1.2.T, and 7.5.

~

t..

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REV 0008 2-51-4.6.G Page 22 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.1.5 ISO responsibilities:

A.

Pzeparing/revising a computerized data base to include all components on the ISZ drawings of Section 2.5.

See Section 7.2.1.A.

B.

Preparing/revising scan plans for each refueling outage of the inspection interval utilizing a computerized data base.

This includes providing additional information provided by NDE level ZII personnel to complete the scan plan, such as NDE Procedure references, calibration standard references, and UT scanning angles.

See Section 7.2.1.B.

C.

Providing NDE level ZZZ approval of scan plan revisions that affect the additional information of Section 7.1.5.B and maintaining a scan plan revision history log.

D.

Providing NDE level IZZ determination if a Request for Relief (RFR) is required because of areas that aze inaccessible or partially inaccessible for examination or because it is determined that conformance with Code requirements is impractical and notifying M/N Engineering of this fact per Sections 7.2.3.E and 7.6.

See Section 7.1.2.J.

E.

Approving contractor NDE procedures, contractor written practices for qualification and certification of NDE personnel and ceztifications of contractor's NDE personnel perfozming ISI/PSI.

See Section 7.2.3.

F.

Providing NDE level IZZ evaluation of successive examinations.

See Sections 7.3.2.E, 7.3.4.E, and 7.12.

RWVh2SI46G

REV 0008 2-SI-4.6.G Page 23 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)

G.

Packaging radiogzaphs for storage and providing them with reader sheets to RM as a life of plant record.

See Sections 7.1.6.C and 7.5.

H.

Providing copies of ZEP-100 NDE procedure revisions and evidence of pezsonnel qualifications to RM as RIMS records for the service lifetime of the plant in accordance with IWA-1400(k).

See Sections 7.1.6.C and 7.5.

Z.

Maintaining as-built calibration standard drawings and the calibration standard material certifications.

See Section 7.4.

7.1.6 Site Records Management (RM) responsibilities:

A.

Issuing controlled copies of ASME Section XZ Code Class Boundary Drawings and ISI Drawings to specifi.ed distribution lists.

B.

Issuing this program as an SZ and providing contzolled copies to M/N Engineering, the ANI/ANIZ, and other organizations as requested.

C.

Maintaining the Site Final Report as a life of plant QA document.

Other records referenced in the final report (work plans, radiogzaphs, etc.)

and NDE procedure revisions, and evidence of personnel qualifications shall be retained foz the service lifetime of the plant.

See Sections 7.1.2.U, 7.1.S.G, and 7.5.

7 ' '

Pzo)ect Management responsibilities:

A.

Pzoviding specific written details foz any augmented requirements foz which they aze responsible per Section 7.12 and determining if a post examination meeting is required.

RAW'I46G

2-SI-4.6.G Page 24 7,0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.1.8 The Authorized Nuclear Znservice Inspector (ANZI) responsibilities:

A.

Performing the duties of IWA-2110, including a detailed review of this ISI Program (Plan) prior to May 24, 1992

[See ZWA-2110(a) (1)] and a review of revisions to this ZSZ Program

[See ZWA-2110(a) (2)]. He shall submit a report of the reviews to the Owner

[See ZWA-2110(a) (3) ].

See Section 7.1.2.D.(2).

B.

Having the prerogative and authorization to require requalification of any operator or procedure when he has reason to believe the requirements are not being met.

7.1.9 Nuclear Assurance and Licensing responsibilities:

A.

Nuclear Assurance and Licensing is responsible foz reviewing, inspection plans, and/or quality assurance programs submitted by contractors.

7 '

I lementation 7.2.1 S stem for Maintainin Status of Examinations A.

Data Base ISO and M/N Engineering shall utilize a computerized data base, for maintaining the status of completed examinations foz ASME Section XI credit and for augmented credit.

See Sections 7.1.5.A and 7.1.5.B.

B.

Scan Plan (1)

The Scan Plan is the primazy scheduling document that is developed by ISO utilizing a computerized data base.

It should contain as a minimum:

components to be examined, Code Examination Category, Code Item Number, methods of exaad.nation, NDE procedure reference, calibration standard reference, ISZ drawing number and sheet

number, and for UT, the scanning angles.

See Sections 7.1.2.G, 7.1.2.F, 7.1.5.B, and 7.1.5.C.

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REV 0008 2-S1-4.6.G Page 25 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)

(2)

Prior to performing examinations, the scan plan shall be approved by M/N Engineering.

(3)

When inservice examinations are performed as a zesult of instructions other than this program (e.g.,

maintenance instructions, work

plans, etc. ), copies of the examination data sheets shall be submitted to M/N Engineering by the performing organization for assignment of a report number and incorporation into the scan plan.

See Section 7.1.2.R.

(4)

During implementation phases, it may become necessary to revise the scan plan.

Scan Plan revisions may be initiated by M/N Engineering, ISO, or by other personnel involved with implementation of the scan plan. All changes shall be coordinated with an M/N Engineering representative

and, as

needed, with the appropriate plant planning and scheduling personnel for facilitating the use of supporting craft personnel.

Revisions to the scan plan shall be controlled in the same manner as the original.

ISO shall maintain a scan plan revision history log. Interim working copies may be handwritten to allow examinations to be pezformed before a formal revision is issued.

These changes shall be approved by M/N Engineering and/or an NDE Level III, if required by Section 7.1.2.G or Section 7.1.5.C.

Approving individuals shall initial and date such changes.

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REV 0008

7. 0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SZ-4.6.6 Page 26 C. Configuration Changes (1)

When major portions of existing pipe or supports are replaced or new systems are

added, a system walkdown should be performed under the direction of M/N Engineering to identify the pipe configuration,

welds, components, and supports that shall be included in the inspection program.

(2) If variations in configuration are discovered or modifications (including additions or deletions),

repairs or replacements aze made during the service lifetime of the unit, the changes shall be marked on field corrected copies of the appropriate drawing listed in Section 2.S by an M/N Engineering representative.

The field corrected copies shall be used in the performance of examinations and as records until the drawing has been revised to reflect the changes.

(3)

M/N Engineering shall be responsible for reviewing the proposed

change, revising the drawings as necessary, and issuing the revised drawings prior to the next refueling outage.

The scan plan shall be revised per Section 7.2.1.B.(4) to reflect any PSZ examinations performed due to the variations in configuration.

R:WVA2SI46G

7.0 REV 0008 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SI-4.6.G Page 27 7 ' '

Notification of Indication (NOI)

A NOI shall be used to officially document and provide a disposition for an indication that exceeds the acceptance criteria of Article 3000 of the ASME Section XI Code or of -3000 of Code Case N-491.

M/N Engineering shall provide/coordinate dispositions for NOI's in accordance with SSP-6.10 and SSP-3.4.

See Sections 7.1.2.Q and 7.7.

B.

Additional Examinations (1) Additional examinations for Class 1

equivalent components (IWB) shall be in accordance with the requirements of IWB-2430. The additional examination samples are defined as those items (welds,

areas, or parts) in a particular examination category and item number.

Engineering Judgement should be documented concerning expansion (or no expansion) into additional systems.

The initial sample is the sample scheduled for examination at a particular outage foz ASME Section XI credit.

(a)

Examinations of the initial sample that reveal indications exceeding the acceptance standards of IWB-3410-1 shall be extended to include additional examinations in the same outage as the initial examinations, except for volumetric and surface examinations where IWB-3112(b) is applicable.

The flaws detected by volumetric or surface examinations that meet the nondestructive examination standards of NB-2500 and NB-S300, as documented in QA records, shall be acceptable.

The first additional examination sample shall include items scheduled for this and the subsequent period. If examinations for that item are not scheduled in the subsequent

period, the most immediate period containing scheduled examinations of that item shall be examined.

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REV 0008 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SZ-4.6.6 Page 28 (b)

Zf the first additional examinations of (1)(a) reveal indications exceeding the acceptance standards of Table IWB-3410-1 except where ZWB-3112(b) is applicable, further additional examinations shall be performed during the outage.

The second additional examination sample shall include all the items of similar design, size and function within the system under examination.

(2) Additional examinations foz Class 2

equivalent components (ZWC) shall be selected per ZWC-2430. If it is determined (Section 7.1.2.H) that additional examinations are

required, those examinations shall be performed in the same outage as the initial examinations.

The additional examination samples are defined as those items (welds,

areas, oz parts) in a particular examination category and item number.

Engi.neering

)udgement should be documented concerning expansion (or no expansion) into additional systems.

The initial sample is the sample scheduled for examination at a particular outage for ASME Section XI credit.

(a)

A first additional sample shall be selected for those initial samples that detect indications exceeding the allowable standards of IWC-3000, except where the flaw is acceptable under IWC-3112(b). The first additional sample shall include approximately the same number of items examined in the initial sample.

The items selected should be those available in the interval sample that have the longest service time from its previous inservice examination.

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REV 0008

7. 0 INSTRUCTION STEPSI ELEMENTS (Continued) '-S1-4.6.G Page 29 (b) If the additional examinations of (2)(a) detect indications exceeding the acceptance standards of IWC-3000, further additional examinations shall be performed during the outage.

The second additional sample shall include the remaining numbez of items of the interval sample not examined in the initial or first additional sample. If no items remain in the interval sample, a notification of the first additional sample results shall be provided to Site Engineering as described in Section 7.2.2.B.(4).

(3) Additional examinations foz component supports (IWF) shall be in accordance with

-2430 of Code Case N-491.

(a)

Zf component supports of the initial sample must be sub)ected to corrective measures in accordance with (N-491)-3000, the component supports immediately ad)acent to those for which corrective action is required shall be examined. Also, the examinations shall be extended to include a first additional sample that includes supports within the system, equal in numbez and of the same type and function as those scheduled for examination during the period.

(b)

When the additional examinations of (3) (a) zequize corrective measures in accordance with (N-491)-3000, a second additional sample of the remaining component supports within the system of the same type and function as in (3)(a) shall be examined.

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REV 0008

7. 0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-S1-4.6.G Page 30 (c)

When the additional examinations of (3)(b) require corrective measures in accordance with (N-491)-3000, examinations shall be extended to include a third additional sample of all nonexempt supports potentially sub)ect to the same failure modes that required corrective measures in (3) (a) and (3)(b). These additional examinations shall include nonexempt component supports in other systems when support failures requiring corrective measures indicate non-system related failure modes. At the request of M/N Engineering, Site Engineering shall make the determination of failure mode applicability and select the third additional sample.

(d)

When the additional examinations of (3)(c) require corrective measures in accordance with (N-491)-3000, examination shall be extended to those exempt component supports that could be affected by the same observed failure modes'nd could affect nonexempt components.

At the request of M/N Engineering, Site Engineering shall make the determination of failure mode applicability and select a fourth additional sample of all component supports on exempt components that could affect nonexempt components.

See Section 7.1.3.D.

(4) After completion of the additional examinations, ASME Section XZ code requirements for additional examinations are complete.

Zf the final sample examinations reveal indications exceeding the acceptance standards of Article 3000 of ASME Section XZg M/N Engineering shall notify Site Engineering to evaluate the indications and make recommendation(s) for further action, if needed.

See Section 7.1.2.Z.

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REV 0008 7.2.3

Examinations 2-SI-4.6.6 Page 31 NDE shall be performed in accordance with IWA-2200 of ASME Section XI utilizing the NDE procedures of IEP-100 or approved contractor procedures.

Personnel performing NDE operations shall be qualified and certified in accordance with IWA-2300 of ASME Section XI as specified in IEP-200.

C.

The inservice examinations shall be performed by M/N Engineering, ISO, or contractor personnel.

Contract preparation, administration, and supervision shall be the responsibility of M/N Engineering.

Inspection plans and/or quality assurance programs submitted by contractors shall be reviewed and approved by Nuclear Assurance and Licensing prior to use. All contractor NDE procedures used during the inspection pzogzam shall be reviewed and approved by ISO using IEP-100 as a guideline.

See Section 7.1.S.E.

D.

In accordance with IWA-2600, a reference system shall be established for all welds and areas sub)ect to surface oz volumetric examination.

Each such weld and area shall be located and identified by a system of reference points.

The system shall permit identification of each weld, location of each weld center line, and designation of regular intervals along the length of the weld.

When less than the required ASME Section XZ code examination volume or area is examined, the percentage examined shall be documented on the examination data sheet.

The cause of the limi.tation shall be clearly specified as a part of the data sheet documentation.

An NDE level ZZZ representative shall review the limitations or impractical examinations during the refueling outage and determine if a code examination was achieved

. Zf one was not achieved, the NDE level III representative shall notify M/N Engineering immediately to determine if a large enough examination volume or area percentage was achieved to qualify for request for relief action in accordance with Sections 7.1.5.D and 7.6. Another component may be selected for a substitute examination if sufficient examination coverage was not achieved.

See Section 7.1.2.J.

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REV 0008 7.0 INSTRUCTION STEPS/ELEME?PZS (Continued) 2-SI-4

~ 6 '

Page 32 7.3 Com onents Sub ect to Examination 7.F 1 ASME Cl ass 1

E ivalent Co onents Sub ect to Examination (IWB)

A.

ASME Class 1 equivalent systems (including the components and integral attachments contained therein, but excluding the supports) subject to examination are:

(1)

Control Rod Drive Hydraulic System (CRD),

(2)

Core Spray System (CS),

(3)

Feedwater System (PW),

(4)

High Pressure Coolant Injection System (HPCI),

(5)

Main Steam System (MS),

(6)

Reactor Core Isolation Cooling System (RCIC),

(7)

Reactor Pressure Vessel (RPV),

(8)

Reactor Water Cleanup System (RWCU),

(9)

Recirculation System (RECIR)f (10) Residual Heat Removal System (RHR), and (ll) Standby Liquid Control System (SLC).

B.

The specific components subject to examination are identified on ISI drawings listed in Section 2.S.

Class 1 valves aze further defined in Section 8.3.

The number of components within each system, the number selected for examination during the interval and the number selected for examination by period are provided in Section 8.1 Examination

Schedule, Part 1 -Class 1 Equivalent (IWB)

Components.

C.

The rules of IWB-1220 (a) and (b) have been used to exempt components from examination and establish the numbers in Section 8.1, Part 1.

Specifically, piping NPS 1 and smaller and components and their connections in piping NPS 1

and smaller are exempt from NDE examinations.

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REV 0008 2-SI-4

~ 6. G Page 33 7.0 INSTRUCTION STEPS/ELEM~VTS (Continued)

D.

ASME Class 1 equivalent piping and components that meet the size exemption listed in reference 2.9.2 are exempt from the Class 1 requirements of 10CFRSO. SSa (c) (1).

The exempted piping components would then be considered ASME Class 2 equivalent since they are part. of the reactor pressure coolant boundazy, but excluded from classification as ASME Class 1.

The associated piping. component sizes are 2-inch schedule 40 (water) and 4-inch schedule 40 (steam) or smaller inside diameter, which are exempt from examination in accordance with IWC-1220.

7.3.2 Selection of ASME Class 1

E ivalent Com onents All Examination Category B-F circumferential welds shall be examined in the Interval with approximately 1/3 examined in each Period.

The Code basis foz this selection of Item Numbers B5.130, B5.140, and B5.150 is Table 1WB-2500-1, Examination Category B-F, 1986 Edition of ASME Section XI.

All carbon and low alloy steel (similar metal) nozzle to safe end welds shall be examined this interval. Additional Examination Category B-J circumferential welds that were not examined in the first interval shall be selected to provide a

25 'percent sample this interval. Continuation of this selection method during the third and fourth intervals shall result in examination of approximately 90% of the Examination Category B-J circumferential welds over the life of the plant.

BFN does not have stress level calculations as required for selection per Table IWB-2500-1, Examination Category B-J, NOTE: (1)(b).

The Code basis for this method of selection of Item Numbers B9.11, B9.21, B9.31, B9.32, and B9.40 is Table IWB-2500-1, Examination Category B-J, 1986 Edition of Section XI except the extent of examination is detezmined by the requirements of Table IWB-2500 and Table IWB-2600, Examination Category B-J, 1974 Edition with Addenda through Summer 1975 as allowed by 10CFR50.SSa(b)

(2) (ii).

See Section 4.1.

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REV 0008 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SZ-4. 6. G Page 34 C.

ASME Class 1 equivalent longitudinal welds, Examination Category B-J, Item Numbers B9.12 and B9.22 shall be selected for examination by virtue of intersecting a circumferential weld (Item Number B9.11 oz B9.21) selected foz examination.

The examination of longitudinal welds is in accordance with the alternative described in Code Case N-S24.

D.

The entize length of each circumferential weld selected shall be examined, unless otherwise noted or if a physical limitation exists.

Examination shall include intersecting longitudinal welds in accordance with Code Case N-524.

E.

Successive Inspections of ASME Class 1

equivalent components shall be in accordance with IWB-2420(a),

ZWB-2420(b) and IWB-2420 (c).

(1)

ZWB-2420(a) shall be utilized except for Examination Category B-K-1 integral attachments and Examination Category B-J welds.

The reasons are the

'odification of the integral attachments (B-K-1) in con)unction with the support modifications explained in Section 7.3.6.F and the extent of examination for B-J welds established in Section 7.3.2.B.

(2)

Indications, evaluated in accordance with IWB-3132.4 or IWB-3142.4 qualifying for continued service, shall be reexamined in the next three inspection periods.

(3)

Zf the reexaminations reveal essentially no change in the indication for the three periods, the examination schedule shall revert to the original schedule.

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REV 0008 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SI-4.6.G Page 35 7.3.2.1 Reactor v ssel Interior The space above and below the vessel core that is made accessible by the removal of components during normal refueling outages shall be visually examined during the first refueling outage and at subsequent refueling outages at approximately thzee-year intervals.

The integrally welded core support structures and interior attachments (specimen holding bracket, etc.) to the reactor vessel shall be visually examined.

The examination shall include 100 percent of the visually accessible attachment welds and core support surfaces.

The attachments are: dryer hold down

brackets, dryer support brackets, guide rod brackets, feedwater sparger brackets, core spray sparger brackets, surveillance specimen holder brackets,

)et pump riser support brackets and shroud support.

The core support structure consists of the top guide and the core plate.

All augmented examination requirements and commitments foz BFN vessel internal examinations during the ISI interval are stated in Section 7.12.11 of this program.

The general surveillance of the reactor vessel internals is in accordance with MSI-0"001-INS001 and/or an approved contractor procedure.

7.3 '

ASME Class 2

E ivalent Co onents Sub ect to Examination (INC)

A.

ASME Class 2 equivalent systems (including the components and integral attachments contained

therein, but excluding the supports) subject to examination aze:

(1)

Control Rod Drive Hydraulic System (CRD),

(2)

Core Spray System (CS),

(3)

High Pressure Coolant In)ection System (HPCI) g (4)

Main Steam System (MS) f RWVA2Sl46G

2-SZ-4 '.G Page 36 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)

(5)

Reactor Building Closed Cooling Water System (RBCCW),

(6)

Reactor Coze Isolation Cooling System (RCZC),

and (7)

Residual Heat Removal System (RHR).

B.

The specific components subject to examination aze identified on ISZ drawings identified in Section 2.5.

The number of components within each system, the number selected foz examination during the interval and the number selected for examination by period are provided in Section 8.1 Examination

Schedule, Part 2 -Class 2 Equivalent (ZWC)

Components.

C.

The rules of IWC-1221 for components within RHR and HPCI (includes containment heat removal) and ZWC-1222 for components in all other systems have been used to exempt components from examination and establish the numbers in Section 8.1, Part 2.

Specifically, the following components are exempt from NDE examinations:

(1)

Vessels, piping, pumpsg valves>

and other components NPS 4 and smallez in all systems'2)

Component connections NPS 4 and smaller in all systems, (3)

Vessels, piping, pumps, valves, other components, and component connections of any size that operate at a pressure equal to or less than 275 psig and at a temperatuze equal to or less than 200 degrees F in systems other than RHR and

HPCZ, and (4)

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

RKVh2SI46G

REV 0008 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 2 SZ-4 '.G Page 37 7,3.4 Selection of ASME Class 2

E uivalent Components A.

One hundred percent of the C-F-1 welds shall be examined in the interval.

To the extent possible, welds examined in the first interval, second and third periods, shall be selected for reexamination in the respective periods of the second interval.

The first period welds shall be selected at random since the 1971 Edition of the Code was utilized for unit 2 during the first period of the first interval and no Class 2

examinations were performed.

The Code basis for this method of selection of Item Numbers C5. 11 and C5.12 is Table IWB-2500-1, Examination Category C-F-l, 1986 Edition of Section XI.

NOTE:

There are no 'Excluded'elds

(< 3/8" nominal wall) at BFH for Examination Category C-F-1.

B.

To the extent practical, Examination Category C-F-2g Item Numbers C5.51, C5.70, and C5.80 circumferential welds that have been previously examined shall be in the 7.5 percent sample selected for examination during the second interval in accordance with IWC-2420(a). Welds examined in the first interval, second and third

periods, shall be selected to the extent practical for reexamination in the respective periods of the second interval.

The first period welds shall be selected at random since the 1971 Edition of the Code was utilized for unit 2 during the first period of the first interval and no Class 2

examinations were performed.

NOTE:

Note (2) of Table IWC-2500-1, Examination Categozies C-F-2 establishes an

'Excluded'elds category foz welds with < 3/8" nominal wall. Excluded welds shall not be examined for Code czedit, since they have no Item Number under the Examination Category.

The Item Number is designated as N/A in Section 8.1 Examination Schedule, Part 1 Class 2

IWC Components.

The excluded welds that aze not exempt are included in the total count to which the 7.5%

was applied to determine the number of C-F-2 weldh to be examined in the interval.

The Code basis for this method of selection of Item Numbezs C5.51, "'C5.70, and CS.81 is Table IWB-2500-1, Examination Category C-F-2, 1986 Edition of Section XZ.

RKVA2SI46G

REV 000$

7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SI-4.6.G Page 38 C.

ASME Class 2 equivalent longitudinal welds, Examination Category C-F-2, Item Numbers C5.52 and CS.82, shall be selected for examination by virtue of intezsecting a circumferential weld (Item Numbers C5.11, C5.41, C5.51 or C5.81) selected foz examination.

The examination of longitudinal welds is in accordance with the alternative described in Code Case N-524.

D.

The entire length of each circumferential weld shall be examined, unless otherwise noted or if physical a limitation exists.

Examinations shall include intersecting longitudinal welds in accordance with Code Case N-524.

E.

Successive Inspections of ASME Class 2 equivalent components shall be in accordance with IWC-2420(a),

IWC-2420(b) and ZWC-2420(c).

(1)

The sequence of component examinations established during the first inservice inspection interval shall be repeated, to the extent practical, as established in this

Section, A. and B. above for Examination Categories C-F-1 and C-F-2, respectively.

(2)

Indications, evaluated in accordance with IWC-3000, qualifying for continued service shall be reexamined in the next inspection period.

(3)

Zf the reexaminations reveal essentially no change in the indication, the examination schedule shall revert to the original schedule.

See Section 7.1.5.F.

R:KWQSI46G

0

REV 0008

7. 0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SZ-4.6.G Page 39 7.3.5 ASME Class 3

E uivalent Components Sub ect to Examination (ZWD)

A.

ASME Class 3 equivalent systems (including the components and integral attachments contained

therein, but excluding the supports) sub)ect to examination are:

(1)

Emergency Equipment Cooling Water System (EECW),

(2)

Fuel Pool Cooling System (FPC),

and (3)

Residual Heat Removal Service Water System (RHRSW), and (4)

Main Steam (MS).

B.

The specific integral attachments sub)ect to examination aze identified on ISI drawings listed in Section 2.5.

The number of integral attachments within each system, the number selected foz examination during the interval and the number selected for examination by period are pzovided in Section 8.1 Examination Schedule, Part 3 - Class 3

Equivalent (IWD) Components.

C.

The rules of IWD-1220.1 and IWD-1220.2 have been used to exempt components from examination and establish the numbers in Section 8.1, Part 3.

Specifically, integral attachments of supports connected to components that are NPS 4 or smallez are exempt from NDE examinations.

RWWQSI46G

REV 0008 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)

I 2-SZ-4.6.G Page 40 7.3.6 Comnonent Su orts Sub ect to Examination (IWF, Code Case N-491)

A.

Component and piping supports shall be examined in accordance with Table -2500-1 (N-491).

Component supports to be examined shall be the supports of those components that are required to be examined under IWB-2500, IWC-2500, and IWD-2500 by volumetric, surface, or visual (VT-1 or VT-3) examination methods.

Piping supports to be examined shall be the supports of piping not exempted under IWB-1220, IWC-1220, and ZWD-1220.

These component and piping supports are within the systems identified in Sections 7.3.1.A, 7.3.3.A, and 7.3.5.A.

The specific supports subject to examination are identified on ZSZ drawings listed in Section 2.5.

The method of support exemption is given in Section 7.3.6.C below.

B.

The number of supports subject to an examination sample plan, the number selected for examination during the interval and the number selected for examination by period aze provided in Section 8.1 Examination Schedule, Part 4 - Component Supports (IWF, Code Case N-491).

C.

Component supports exempt from NDE examinations are those connected to components and items exempted by IWB-1220, IWC-1220, and IWD-1220, and portions of those that aze inaccessible by being encased in concrete, buried underground, or encapsulated by guard pipe. Piping supports exempt from examination shall be the supports of piping exempted under ZWB-1220, IWC-1220, and IWD-1220 and those that are inaccessible by being encased in concrete, buried underground, or encapsulated by guard pipe.

R:WVh2SI46G

REV 0008

7. 0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SI-4 '.G Page 41 0'.

Support examination boundaries shall be in accordance with (N-491) -1300.

Examination and acceptance of variable support settings shall be in accordance with the detailed support drawing.

If a total acceptance range is required and is not given on the detail support drawing, it shall be calculated per IEP-100, N-GP-7 and N-VT-1. See Section 7.1.2.W.

E.

Component supports that have been ad)usted in accordance with (N-491) -3000, repaired, or replaced shall be examined pzior to zetuzn of the system to service per the applicable examinations listed in Table -2500-1.

For systems that operate above 200 degrees F during normal operation, an additional preservice examination shall be performed on the affected component supports during or following the subsequent system heatup and cooldown cycle unless determined unnecessary by evaluation.

This examination shall be performed during operation or at the next refueling outage.

F.

Successive Inspections of component supports shall be in accordance with -2420 (b) and -2420 (c) of Code Case N-491. Utilization of (N-491)-2420(a) is not practical.

The components supports were completely redesigned and modified in the last period of the first interval (forced outage 9/15/84 to 5/24/91) to comply with Generic Letter 79-14. A sequence shall be established this inspection interval that may be used in future intervals.

(1)

A component support subjected to corrective measures in accordance with (N"491)-3000 shall be reexamined in the next inspection period.

(2)

When additional'orrective measures are not zequized by the reexamination of (1) above, the inspection schedule may revert to the original schedule.

0:

RRWQSI46G

REV 0008 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SI-4.6.G Page 42 7.4 Calibration Standards Calibration blocks shall be used foz ultrasonic examination.

The blocks shall be fabricated in accordance with ASME Section V and ASME Section XI. ZSO shall maintain as-built calibration standard drawings and calibration standard material certifications (CMTR's). The calibration blocks shall be stored at the plant site and maintained by M/N Engineezing personnel.

See Sections 7.1.2.X and 7.1.5.I.

7.5 Recozds and Re orts Records and reports shall be in accordance with ASME Section XI, Articles IWA-1400 (k), IWA-1400 (1),

and IWA-6000.

A.

The Inservice Inspection (ISZ)

Summary Report shall

include, as a minimum, the information required by IWA-6220(c) and IWA-6220(d) and shall be submitted to Site Licensing on a schedule that permits submittal to the NRC within 90 days after the refueling outage.

The ISZ Summary Report shall contain:

(a) the examinations and System Pressure Tests associated with ISZ, replacements, and repairs conducted since the preceding summary report; (b)

National Board numbers assigned to the components by the manufacturer, if applicable; (c) identifiers of the components examined including sire, material, etc.;

(d) name and address of manufacturers p

(e) manufacturer's component Z.D.'s, if applicableg (f) date of completion of examinations; (g) name of Inspector verifying examinations, his company and company address; (h) abstract of examinations and tests pezformed; conditions recorded) and corrective measures taken'i) signature of the Inspector; and ()) Owner's Report for ZSZ (NZS-1). The cover sheet shall contain:

(a) the date of document completion, (b) name and address of the Owner, (c) name and address of generating plant, (d) unit designation, and (e) commercial operating date.

R RWQSI46G

REV 0008 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SI-4.6.6 Page 43 B.

A Site Final Report shall be prepared and submitted to RM.

The Site Final Report, and the references therein, shall be maintained as a QA record for the service lifetime of the plant in accordance with IWA-6300. The Site Final Report shall contain:

(a) an index to record file, (b) the inservice and preservice NDE examination reports, (c) the NIS-1 and NIS-2 summary reports.

The Site Final Report shall also contain, as a minimum, reference to:

(a) this ISI Program (inspection plan),

(b) repair records and

reports, (c) replacement records and reports, (d)

NDE Procedures, and (e)

NDE examination records including radiographs and review forms.

C.

Radiographs shall be packaged by ISO and provided to RM for storage as a life of plant record.

See Sections 7.1.S.G, 7.1.6.C, and 7.5.B.

D.

NDE Procedure revisions (IEP-100) and evidence of personnel qualifications shall be maintained by RM as RIMS records foz the service lifetime of the plant.

See Sections 7.1.5.H, 7.1.6-C, and 7.5.B.

E.

Reproduction and microfilming shall meet the requirements of IWA-6320.

7.6 Re ests for Relief (RFR)

Where TVA has determined that Code requirements or examinations aze impractical, TVA shall submit written Requests for Relief (RFR) to the NRC with information to support the need for relief and any proposed alternate examinations.

The impractical Code requirements or relief situation shall be identified as a

part of the Section 8.1 examination schedules in this program and references to a particular RFR shall be included.

When impractical examination requirements aze identified in the field, ISO shall notify M/N Engineering in accordance with Sections 7.1.5.D and 7.2.3.E.

M 4 I shall review and comment on any new RFR's.

The Requests for Relief are contained in Section 8.4 of this programs RWWQSI46G

REV 0008

7. 0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SI-4 '.G Page 44 7.7 Corrective Action Pro ram Any corrective action required as a result of ISI examinations shall be handled in accordance with SSP-3.4.

7.8 Re airs and Re lacements Repair and replacement shall be in accordance with SSP-6.9

~

Preservice inspections (PSI) shall be performed on any component that is repaired,

replaced, or modified that is of an Examination, Category and Item Number as specified in Section 8.1.

The NDE method shall be as specified in Section 8.1.

7.9 S stem Pressure Tests System pressure test and VT-2 examinations shall be in accordance with SSP-8.5.

7 ~ 10 P

and Valve Inservice Testin Pump and valve inservice testing shall be in accordance with SSP-8.6.

7.11 Snubber Inservice Testin IWF-5000 oz (N-491)-5000 is not a part of this program.

Snubber inservice testing shall be in accordance with 2-SI-4.6.H.1.

R:WVA2SI46G

REV 0008 7 '

INSTRUCTION STEPS/ELEMENTS

{Continued) 2-SI-4.6.G Page 4S 7'2 Au ented Examinations Augmented examinations are performed in addition to ASME Section XI code requirements.

The augmented examinations may be zequired by the NRC or be self-imposed by TVA. Typical sources include generic letters, ZE Bulletins, technical specifications, vendor recommendations, and industry experience.

Section 8.1, Part 5 provides a schedule for augmented examinations.

The responsible organization or owner shall have technical and administrative responsibility for each augmented examination identified in this section.

This responsibility shall include scheduling any examinations through the M/N Engineering, tracking the status of examinations, and zeporting completed examinations.

Responsible organizations requesting inclusion of augmented examinations in this section shall submit a written request to the Lead M/N Engineering.

The written request shall include specific details such as requirement

souzce, identification of components requiring examination, examination frequency, examination method, examination area/volume, acceptance criteria, types of flaws anticipated, areas of high

suspect, probability of failure, and reporting requirements.

Copies of the written request shall be submitted to 'M 4 I and the M/N Engineering to facilitate nondestructive examination procedure preparation, establishment of training programs, and pezsonnel familiarization.

Prior to each refuelingoutage, a meeting shall be initiated by the M/N Engineering.

Meeting attendees shall include the responsible organizations, M/N Engineering, M 4 I, and Site Engineering.

The meeting agenda should include examination plans and schedules, updates on industry experience, and any additional pertinent information.

Following the completion of the augmented examination, the M/N Engineering shall report to the responsible organization items such as examination results and changes in results from previous examinations.

The responsible organization shall determine if a meeting with the M/N Engineering and/or other appropriate organizations is necessary to discuss items such as additional examinations to be conducted during the current

outage, trends, lessons

learned, and identify any futuze actions such as changes in the frequency of examination.

SZL's and clarification letters listed in this Augmented Inspection Section provide GE's recommendation foz reactor internals inspection.

The actual scope and criteria for reactor internals inspections will be reviewed and approved by TVA Site Engineering prior to each refueling outage.

Any indications found during inspections will receive a review and will be dispositioned by TVA Site Engineering.

R:KWQSI46G Augmented examinations that require reporting to the NRC shall be the responsibility of the responsible organization.

REV 0008 2-SI-4.6.G Page 46 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.12.1 Weld DSRHR-2-05A Responsible organization:

Site Engineering.

Weld DSRHR-2-OSA has an indication that was determined to be lack of fusion between layers of welding. It shall receive augmented RT and UT examinations each inspection period to monitor the size of the indication. Evaluation of the indication shall be performed by an ISO NDE level III by comparison to previous examinations

~ If theze is any change, Site Engineering shall be formally requested to provide additional evaluation.

See Sections 7.1.3.B and 7.1.5.F.

A report of the examinations shall be forwarded to the NRC with the NUREG-0313 report of Section 7. 12.8.

[NRC/C] Reference NRC Inspection Report 86-03, Open Item 86-03-03 (RIMS L29 860925 984)].

PRISZM Exam Requirement Source:

D01-02.

7.12 '

RPV Claddin Indication Responsible organization:

Site Engineering.

An indication in the RPV cladding was discovered in August 1988 during the RPV interior examination. It is located at 15 degree

azimuth, 32 3/4" below the RPV flange surface.

This indication shall receive a

VT-1 examination in refueling cycles 6, 7, and 8 to determine if there is any degradation.

Evaluation of the indication shall be performed by an ISO NDE level IZZ by comparison to previous examinations.

Zf there is any change, Site Engineering shall be formally requested to provide additional evaluation.

See Sections 7.1.3.B and 7.1.5.F.

A report of the examination shall be forwarded to the NRC with the ZSI Summary Report.

The examination data from the four consecutive cycles shall be evaluated after the cycle 8 refueling outage to determine if further augmented exams shall be required

{RIMS W10 880831

850, W10 880908

873, and B22 880920 022).

PRISIM Exam Requirement Souzce:

D02-02.

R:RVA2S]46G

REV 0008 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SI-4.6.G Page 47 7.12.3 Welds KR-2-14, KR-2-36, KR-2-37, and KR-2-41 Responsible organization:

Site Engineering.

These

welds, which had IGSCC indications that were evaluated to be acceptable for continued operation, shall be reexamined

{UT) in the cycle 6 refueling outage per NRC commitment NCO 850264005

{RIMS L44 860311 803).

Evaluation of the indication shall be performed by an ZSO NDE level IZI by comparison to previous examinations. If there is any change, Site Engineering shall be formally requested to provide additional evaluation.

KR-2-37 has volumetric indications in the base metal that require monitoring in accordance with Engineering disposition.

See Sections 7.1.3.B and 7.1.5. F. A report of the examinations shall be forwarded to the NRC with the NUREG-0313 report of Section 7.12.8.

PRISIM Exam Requirement Source:

D03-02.

7.12 '

HPCI P

Dischar e

Su ozt Ins ection Followin

~In ection NRC commitment NCO850144002 for the augumented examination of the supports on the HPCZ discharge line following an injection was revised on March 7, 1995.

The revised commitment requires the examination of the HPCI discharge line supports in accordance with the normal ASME Section XI requirements.

The revised commitment number is NCO950027001.

~

I; RWVA2SI46G

REV 0008 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SI-4.6.G Page 48 7.12.5 Weld GR-2-64(OL)

[NRC/C)- Responsible organization:

Site Engineering.

This structurally over-layed weld shall be one of the IGSCC Examination Category E welds examined during the cycle 8 refueling outage.

A report of the examinations shall be forwarded to the NRC with the NUREG-0313 report of Section 7.12.8.

PRISIM Exam Requirement Source:

B02-02.

[NC094028101)

RWVh2S[46G

REV 0008 2-SI-4.6.G Page 49 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7'2 '

CRD Return Line Reroute Responsible organization:

Site Engineering.

The augmented examination requirements of the CRD return line reroute are contained in NUREG 0619.

The welded connections joining the rerouted CRD return line to the reactor water cleanup system shall be ultrasonically examined during the Cycle 6 refueling outage.

The weld RCRD-2-45 shall be ultrasonically

examined, including the base metal on each side within one wall thickness (nominal wall 0.531"). The pipe into which the CRD return flow is connected shall also be examined by ultrasonic methods to a distance of at least one pipe diameter downstream of the welded connection.

Welds RCRDS-2-3 and RCRD-2-44 shall be ultrasonically examined along with the pipe on the downstzeam side.

Reference memorandum from NRC to TVA dated July 2, 1981 RZMS

() A02810708001.

Reporting to the NRC is zequired within 6 months of completing an outage duzing which an inspection was performed.

The report of these examinations shall be included with the ZSZ Summary Report unless a special report is deemed necessary by M/N Engineering.

Refer to NUREG-0619, Section 8.3 for information to be included.

PRZSZM Exam Requirement Source:

B01-02.

7.12.7 Feedwater Norzles Responsible organization:

Site Engineering.

The augmented examination requirements for the feedwater nozzles is contained in NUREG-0619. An ultrasonic examination of all the feedwater nozzle safe ends/

bores, and inside blend radii are required every second refueling outage.

The feedwater spazgers shall be visually examined every fourth refueling outage (MSI-0-001-ZNS001). A liquid penetrant examination of the nozzle bore and inner radius is required every nine refueling cycles or within 135 staztup/shutdown cycles based on the replacement date.

Reporting is required within 6 months after the outage when an inspection was performed.

The report of these examinations shall be included with the ZSZ Summary Report unless a special zepozt is deemed necessary by M/N Engineering.

Refer to NUREG-0619, Section 4.4.3 for information to be included.

PRISIM Exam Requirement Source:

B01-02.

~

L R:WVA2SI46G

2-SI-4.6.G Page 50 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.12.8 Au ented Examination of Austenitic Stainless Steel and Dissimilar Metal Welds Susce tible to IGSCC (Generic Letter 88-01 and NUREG-0313, Rev.

2)

Responsible organization:

Site Engineering.

Austenitic stainless steel and dissimilar metal circumferential welds in piping four inches or larger NPS that contain reactor coolant at a temperature above 200 F during power operation shall be examined in accordance with the requirements of Generic Letter 88-01 and NUREG-0313, Rev. 2.

Sample expansion shall be in accordance with Generic Letter 88-01 (GL 88-01) based on the IGSCC Category (A, B, C,

D, or E) as defined in the generic letter.

The welds requiring examination pez this paragraph are listed in Section 8.2 - Part 1. Stainless steel and dissimilar metal welds that are exempt from examination because they contain coolant of 200 degrees or less aze listed in Section 8.2 Part 2.

In addition to the requirements of Section 7.2.3.A for examination procedures, the examination procedures used for IGSCC examinations shall satisfy the requirements of GL 88-01.

R:WWQSI46G

REV 0008 2-SZ-4.6.G Page 51 7-0 INSTRUCTION ST~>S/ELEMENTS (Continued)

Zn addition to the requirements of Section 7.2.3.B for personnel qualifications, personnel shall be qualified by the program described in GL 88-01 for performing IGSCC examinations.

The examination schedule is based on the IGSCC category and shall be as indicated.

IGSCC CATEGORY EXAMINATION EXTENT AND SCHEDULE 25 percent every 10 years (at least 12 percent in 6 years).

50 percent every 10 years after initial post-stress improvement (SI) examination (at least 25 percent in 6 years).

100 percent within next 2 refueling cycles after initial post-SI examination (at least 50 percent in 6 years).

100 percent every 2 refueling cycles.

50 percent next refueling cycle after crack discovery and/or overlay.

100 percent every 2 refueling cycles thereafter.

100 percent every refueling outage.

100 percent during each outage.+

~The two IGSCC Category G welds (DRHR-2-03B and -13B) aze to be examined (VT-2) for leakage during each refueling outage per NRC Letter A02 930223 002.

NOTE:

The ANZI shall be required to verify these examinations.

Any flaws identified that do not meet the IWB-3500 criteria for continued operation without evaluation, or a change found in the condition of the welds previously known to be cracked, shall be reported to the NRC under the guidelines of NUREG-0313, Rev. 2.

PRZSIM Exam Requirement Source:

B02-02.

RWWQSI46G

7.0 REV 0008 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SI-4 '.G Page 52

7. 12. 9 Technical S ecification Surveillance Re uirement 4.6.6.2 Responsible organization:

Site Engineering. Additional ultrasonic examinations shall be performed each inspection interval on certain circumferential pipe welds to provide additional protection against pipe whip in accordance with Technical Specification Surveillance Requirement 4.6.G.

The welds requiring examination each interval for pipe whip protection are:

TCS-2-407, TCS-2-423~

TSCS-2-408~

TSCS-2-424, GFW 2 09'FW 2

12~

GFW 2 15~

GFW 2 26~

GFW 2 29~

GFW-2-32, KFW-2-13, KFW-2-31, KFW-2-38, KFW-2-39 g THPCI-2-070, THPCI-2-070A, THPCI-2-071, THPCI-2-072/

GMS-2-06'MS-2-15'MS-2-24, GMS-2-32, KMS-2-024/

KMS 2 104@

DSRHR 2 04'SRHR 2

06@

DSRHR 2 07$

DSRWC-2-03, DSRWC-2-04, DSRWC-2-05'ND DSRWC-2-06.

A report of these examinations shall be included with the ISI Summary Report.

PRISIM Exam Requirement Source:

B04-02.

7.12.10 RPV Shell Weld Examination Responsible organization:

M/N Engineering.

The RPV shell welds, Examination Category B-A, Item Numbers Bl.ll and B1.12 shall be examined during the second inspection interval in accordance with the guidance of

'0 CFR 50.55a(g) (6) (ii) (A) per TVA's revised commitment to the NRC dated March 25, 1993 (R08 930325 853).

TVA shall take ASME Section Xl credit for these examinations as satisfying the requirements of Table 2500-1, Examination Category B-A, Item Number Bl.10. A report of these examinations shall be included with the ISI Summary Report.

PRISIM Exam Requirement Source:

B05-02.

I R:WVA2SI46G

REV 000$

7. 0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SI-4.6 '

Page 53 7.12 F 11 RPV Interior Examinations Responsible Organization:

Site Engineering.

In addition to the code required ISI examinations in Section 7.3.2.1, the following augmental examinations shall be performed during the inspection intervals at thefrequencies as specified in the paragraphs below unless specified otherwise by Site Engineering.

PRISIM Exam requirement Source:

B06-02.

7.12.11.1 Core Spray Spargers and Associated Piping Responsible organization:

Site Engineering.

The augmented examination requirements of the core spray spargers and associated piping is included in MSI-0-001-ZNS001 and/or an approved contractor procedure, which implements ZE Bulletin 80-13.

The creviced areas of the coze spray piping welds inside the RPV shall be visually examined utilizing enhanced methods and/or ultrasonically examined in accordance with the recommendations of SIL-289.

The spargers shall be visually examined each refueling outage.

Volumetric techniques may be used to evaluate any indications.

The reporting criteria is listed in MSZ-0-001-Ixsotl. h xepott of these examinations shall he included with the ZSZ sumamty sepoxt.

7.12.11.2 Coze Support Shroud SIL-572 Perform inspection of the Core Support Shroud to the recommendations of SIL-572.

This consist of performing visual or UT inspection of the accessible weld areas of the shroud.

The implementation interval for the Unit 2 shroud inspection recoamended in SZL-572 shall start with the Unit 2 Cycle 7

refueling outage. If no indications aze found, the shroud shall be inspected every second refueling outage following Cycle 7.

If indications aze found, the shzoud should be inspected each following refueling outage or as directed by an engineering analysis of the indications.

R.KVA2SI46G

7.0 INSTRUCTION STEPS/ELEMENTS REV 0008 (Continued) 2-SZ-4.6.G Page 54 7.12.11.3 Shroud Suppozt Access Hole Covers SZL-462 Inspect the Shroud Support Access Hole Covers pez the recommendations in SIL-462.

This consist of performing UT inspection of the access hole cover weld areas.

The implementation interval for the Unit 2 access hole cover inspection recommended in SIL-462 started in the Unit 2 Cycle 6

refueling outage.

Based on current operation (16 to 18 month fuel cycles) the access hole covers shall be inspected every second refueling outage following Cycle 6. If 2 year operating cycles aze utilized, the covers shall be inspected each refueling outage.

7.12.11.4 Shroud Head Bolts SZL-433 Perform a UT inspection on the original designed Shroud Head Bolts to the zecommendations of SZL-433. These SZL's are applicable to the "Original Design" bolts only and do not apply to "New Design" non-czeviced bolts.

The implementation interval for the Unit 2 shroud head bolt inspection recommended in SIL-433 started during the Unit 2 Cycle 5 outage.

Any installed "Old Design" bolts shall be inspected each refueling outage following Cycle 5 oz as required by an engineering disposition of the installed old design bolts.

7.12.11.5 Coze Spray T-Box Welds SIL-289 Perform visual inspection of the Core Spray T-Box front cover plate weld and the Coze Spray T-Box to thezmal sleeve weld )oint to the recommendations of SIL-289. Per SIL-289, the inspection should be performed in con)unction with NRC IE Bulletin 80-13 inspections of the coze spray sparger which are performed each outage.

The implementation interval for the Unit 2 Core Spray T-Box inspection recommended by SZL-289 started in the Unit 2 Cycle 5

outage.

The Coze Spray T-Box shall be zeinspected during each subsequent refueling outage following the Cycle 5 outage.

RWVA2SI46G

REV 0008 2-SI-4.6.G Page 55 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.12. 11.6 Jet Pump Beams SIL-330 Perform inspection of the )et pump beams per the recommendations in SIL-330. SIL-330 recommends that beams with a modified heat treatment be inspected per NUREG CR-3052.

Per NUREG CR-3052, UT inspection of beams manufactured with a modifi,ed heat treatment shall be performed at 10 year intervals.

The Unit 2 beams were replaced with beams manufactured from a modified heat treatment material during the Cycle 5 outage.

The installed Unit 2 beams aze original'quipment (G001) material with a High Temperature Anneal (HTA) heat treatment.

Per NUREG CR-3052, the inspection interval of the beams shall be once every 10 year interval. All Unit 2 beams shall be inspected during the current second 10 year code inspection interval and once during each subsequent 10 year interval.

7.12. 11.7 Jet Pump Sensing Lines SIL-420 Perform visual inspect of the Jet Pump Sensing Lines when convenient pez the recommendations of SIL-420. The recommendation is to inspect the instrument lines when equipment is available and when inspections are being performed in the.

general area of the instrument lines.

The inspection interval for the Unit 2 Jet Pump Sensing Lines shall start during the Cycle 7 outage.

The sensing lines shall be inspected during each refueling outage when equipment is available and when other adjacent area inspections aze performed.

R:WWQSI46G

REV 0008 7

~ 0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SI-4.6.G Page 56 7.12.11.8 Jet Pump Throats SZL-465 Perform visual inspection of the Jet Pump Throats per the recommendations of SZL-465.

The inspection interval for Jet Pump Throats will be determined as required by engineering review of )et pump flow data.

Per SIL-465, if engineering review of )et pump flow data indicates a degraded flow performance condition, the throats of at least 2 get pumps throats should be inspected during the next refueling outage.

7.12.11.9 Jet Pump Riser Braces SZL-551 Perform visual inspection of the Jet Pump Riser Braces per the recommendations in SIL-551. This consists of visually inspecting 50% of the riser brace welds during each refueling outage.

The implementation interval for the Unit 2 Jet Pump Riser Brace inspection recommended in SZL-551 shall start with the Unit 2 Cycle 7 refueling outage.

Riser Braces on Jet Pump numbers 1 through 10 shall be inspected during the Cycle 7 outage, and then repeated at every second refueling outage following Cycle 7. Riser Braces on Jet Pump numbers 11 through 20 shall be inspected duzing the.

Cycle 8 refueling outage and then repeated during every second refueling outage following Cycle 8.

R:WVA2SI46G

REV 0008 I

7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SI-4. 6.G Page 57 7.12.11.10 Jet Pump Adjusting Screws SIL-574 Perform visual inspection of the Jet Pump Adjusting Screws per the recommendation of SIL-574. This consist of inspecting the adjusting screws on each Jet Pump during each refueling outage.

The implementation interval for the Unit 2 Jet Pump Adjusting Screws inspection shall start with the Unit 2 Cycle 7 outage.

Inspection of the adjusting screws shall be conducted during the Cycle 7 outage and during each subsequent refueling outage following Cycle 7.

7.12.11.11 Top Guide SIL-554 Perform visual inspection of the Top Guide per the recommendations of SIL-554. This consists of inspecting the Top Guide when fuel and blade guides have been removed as part of refueling operation.

GE Letter No. 's BFSE 94-001 f BFSE 94-002 indicates that based on neutron fluence levels top guide inspection should be performed.

The implementation interval for the Unit 2 Top Guide inspection shall start with the Unit 2 Cycle 8 outage.

Inspection shall be performed during the Cycle 8 outage and during subsequent refueling outages as.

conditions allow (i.e., fuel and blade guides aze removed as part of refueling operations)

. Per the GE letter, inspection of 5 to 10 percent of the top guide cell areas each outage is adequate as allowed for by refueling operations.

RWWQSI46G

REV 0008 2-SI-4.6.G Page 58

7. 0 INSTRUCTION STEPS/ELEMENTS

{Continued)

7. 12 ~ll.12 IRM/SRM Dry Tubes SZL-409 Perform visual inspection of the IRM/SRM Dry Tubes pez the recommendations in SIL-409. The recommendations are to inspect the original design dry tubes following the fourth refueling outage after installation and then at every second refueling outage.

Modified design tubes should be inspected the sixth refueling outage after installation and then at every third refueling outage.

As of the Unit 2 Cycle 5 outage all but one dry tube was originally installed equipment. All dry tubes were inspected during the Cycle 5 outage.

The implementation interval foz the Unit 2 Dry Tube inspection recoaamended in SZL-409 started with the Unit 2 Cycle 5 outage.

All originally installed Dry Tubes shall be inspected at every second refueling outage following the Cycle 5 outage.

The new tube installed during the Cycle 5

outage shall be inspected during the Cycle 11 refueling outage and then at every third refueling outage following Cycle 11.

Any new tube installed during future refueling outages shall be inspected at the frequency prescribed in SZL-409.

7.12.11.13 Unit 2 Steam Dryer Drain Channel Welds Steam dryer drain channel welds on Unit 2 which have received weld buildup shall be inspected to the requirements provided in GE Letter No.

BFSE 94-002 dated 1/18/94.

All Unit 2 steam dryer drain channel welds were repaired and mitigated by weld buildup during the Cycle 5 outage.

The implementation interval for the drain channel inspection started in the Unit 2 Cycle 5 outage.

Per GE Letter No.

BFSE 94-002 one drain channel weld shall be inspected every second outage following the Cycle 5 baseline inspection.

Previously cracked welds should be inspected first in the inspection sequence.

RRN2SI46G

REV 0008 2-SI-4. 6. G Page 59 7.0 J'tSTRUCTIQN STEPS/ELEMENTS (Continued) e

7. 12. 11 ~ 14 Unit 2 Steam Dryer Bracket (Incident Investigation No. II-B-93-026)

Perform visual inspection of the unit 2 steam dryer bracket located on the northwest side of the dzyer. This bracket was damaged during the Unit 2 Cycle 6

outage.

An engineering disposition of the damaged bracket required inspection of the bracket following one cycle of operation.

(Reference Incident Investigation No.

II-B-93-026.) Visual inspection of the bracket shall be performed and compared to the Cycle 6 inspection results to determine if additional degradation has occurred. If any additional degradation has occurred an engineering review of the brackets condition shall be performed.

An engineering analysis shall be performed on any change of condition of the bracket.

Additional subsequent inspections will be performed if required by this engineezing analysis.

7.12.11.15 Instrument Nozzle Safe Ends SIL-571 Perform UT and visual inspection of the stainless steel level instzumentatlon nozzle safe ends and stainless steel core differential pressurelstandby liquid control (SLC) nozzle safe ends per the recommendation of SIL-571. The recommendations aze to perform a visual leak check of the safe ends during the drywell leak check effort performed each outage.

Insulation femoval is not necessary to perform the leak check.

A UT inspection of the accessible areas of all the safe end base material shall be performed.

Per GE Letter No.

BFSE 94-005 these stainless steel safe ends should be UT inspected following 15 years of hot operation time and then at a frequency of once every second 24 month fuel cycle oz once every third 18 month fuel cycle as applicable.

~

L R:KWQSI46G

REV 0008 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 2-SI-4. 6. G Page 60 The implementation interval shall stazt with the Unit 2 Cycle 7 refueling outage.

Leakage inspections shall be performed as described during the Cycle 7 outage and during each subsequent refueling outage.

Based on current 16-18 month refueling cycles UT inspection shall be performed during the Cycle 9 refueling outage and then at every second zefueling cycle following Cycle 9.

7.12.11.16 Core Spray and Recirc Inlet Safe Ends Perform UT inspection of the Core Spray and Recirc Inlet Safe Ends per the recommendation of GE Letter No.

BFSE 94-007.

The Unit 2 Core Spray and Recirc Inlet Safe Ends were replaced during the Cycle 5 outage.

The safe ends were replaced with IGSCC resistant

material, and in the case of the Recirc-inlet safe ends an improved design was used which eliminated crevices.

These changes in materials and design mitigate the possibility of future Inter Granular Stress Corrosion Cracking (IGSCC).

Per guidance provided in NRC Generic Letter 88-01 (NUREG 0313 Rev 2) and the recommendation of GE Letter No.

BFSE 94-007, these safe ends shall be inspected at the frequency established for Category "A" weldments.

The accessible areas of the safe end base material which has exposure to the annulus/crevice azea czeated by the thermal sleeve shall be inspected with UT. This inspection should be conducted in conjunction with the augmented UT inspection of the safe end to nozzle weld. Techniques previously used to inspect for safe end IGSCC cracking should be utilized as practical in the inspection effort to detect Internal Diameter (ID) initiated IGSCC indications.

The implementation interval started with the Unit 2 Cycle 5 outage.

The described safe end base material shall be inspected at the same interval as category "A"

weldments. Ideally the inspection should be performed in conjunction with the safe end to nozzle welds which aze also classified category "A".

RWWQS(46G

REV 0008

7. 0, ZNSTRUCTION STEPSl ELEMENTS (Continued) 2-SI-4 '.G Page 61 7.12.11.17 Top Guide and Core Plate Bolting Examination GE SZL 588 The top guide and coze plate bolting should be VT-3 examined during the Unit 2, cycle 8 outage (TROI item GE SIL 588, seq

04) in accordance with GE SIL 588.

The top guide examination includes the accessible areas of the members which provide the load path between the top guide and the shroud.

The coze plate bolt inspection should assure that their locking devices are in place for the bolts that become accessible during normal refueling activities.

R:WWQSI466

2-SZ-4 '.6 Page 62 7.0 INSTRUCTION STEPS/ELEMENTS

{Continued) 7.13 Voluntar Examinations Certain examinations are done on a voluntary basis to obtain additional information to support inservice inspections or to resolve a problem identified through the corrective action program.

Key voluntary examinations are defined and documented in this Section.

7. 13. 1 Examination of RPV Nuts and Washers based on FZR BFQ910238FIR and Other Voluntar Examinations PRISIM Exam Requirement Source:

V01-02. Unit 2 RPV nuts and washers shall be reexamined in cycle 6 based on FIR BFQ910238FZR.

This will be a one time volunteer examination to assuze-that nut and washer records include their unique position (1 through

92) with respect to the RPV stud locations in the flange.

Zn the Core Spray System, welds TCS-2-4XX received a pze-stress improvement voluntary examination during cycle 6 to assure that IGSCC did not exist.

R:WVh2SI46G

REV 0008 2-SZ-4.6.G Page 63 8.0 TABLES/ATTACHMENTS This Section contains Examination Schedules (8.1), List of Welds requiring examination by Generic Letter 88-01 (8.2), Class 1 Valve List (8.3),

and Requests for Relief (8.4).

A list and status of the Requests for Relief contained in Section 8.4 is presented here:

RFR ZSI-2-1, Reactor Pressure Vessel (RPV) Support Integral Attachment withdrawn pending examination performance.

(2)

RFR ZSI-2-2, Reactor Pressure Vessel (RPV) Threads in Flange.

withdrawn.

(3)

RFR ISZ-2-3, Reactor Pressure Vessel (RPV) Nozzle to Vessel Head Weld (N6 Nozzle).

Submitted to the NRC as a part of Revision 2 of this SZ.

(4)

RFR ZSI-2-4, Class 1 Piping Welds.

Submitted to the NRC as a part of Revision 2 of this SI.

(5)

RFR ISI-2-5, Longitudinal Welds in Class 1 and 2 Piping.

Submitted to NRC for utilization of Code Case N-524.

Incorporated in Revision 4 of this SI.

(6)

RFR ZSI-2-6, Reactor Pressure Vessel (RPV) nozzle to vessel welds.

Incorporated in Revision 5 of this SI.

(7)

RFR ISZ-2.7, Class 1 Integral Welded Attachments.

Incorporated in Revision 5 of this SI.

R:WWQSI46G

REV 0008 2-SI-4 '.G Page 64 SECTION 8.1 EXAMINATIONSCHEDULE PART 1 - CLASS 1 EQUIVALENT (IWB) COMPONENTS Examination Item Number of System/

Category No.

Components Subtotal B-A B1.11 5

RPV Second Inspection Interval Sample First Period Sample Second Period Sample Third Period Sample Components Shown On ISI Drawing 0

CHM-2046-C Exam(s)

Required Remarks RPV Shell Circ Weld See Section 7.12.10 B-A B-A B-A B1.12 Bl-21 Bl.22 15 16 RPV RPV RPV CHM-204 6-C ISI-0408-C ISI-0408-C UT UT RPV Shell Lo Weld See Sect n

7.12.10 RPV Circ Top Hd Wld (RCH-2-1C)

RPV Circ Bot Hd Wld (C-S-BH)

RPV Mer Top Hd Wld (RCH-2"XV)

RPV Mer Bot Hd Wid (V-BH-X)

B-A B-A B-A B1.30 1

B1.40 B1.40 RPV RPV RPV CHM-2046-C ISI-0408"C ISI-0408-C UT RPV Flg Weld (C-5-FLG)

RPV Hd-Flg Weld (RCH-2-2C)

RPV Hd-Flg Flex Area (RCH-2-2C-FI R.'WWQSI46G 1

RBV0008 2-SI-4.6.6 Page 65 SECTION 8.1 EXAMINATIONSCHEDULE PART 1 - CLASS 1 EQUIVALENT (IWB) COMPONENTS 1Continued)

Examination Item Category Po.

B-A B1.51 Number of Components N/A System/

Subtotal Second Inspection Interval Sample N/A First Period Sample Second Period Sample Third Period Sample Components Shown On ISI Drawing I Exam(s)

Required Remarks RPV Repair Weld(s)

None B-B B-D B3.90 N/A 31 31 10 10 CHM-2046-C c

ISI-0292-C C

ISI"0380-C None RPV Noz-Ves Wld B-D B-E B-E B3.100 31 B4.11 B4.12 185 RPV RPV RPV 31 10 10 cHM-2046-c a

ISI-0292-C C

ISI-0380-C CHM-2046-C ISI-0292-C UT RPV Noz IR RPV Partial PENX. Nozzles VT-2 CRD Nozzle Interval Hydro B-E B-F B4.13 B5.10 55 17 RPV 17 14 ISI-0292-C ISI"2070-C ISI-2071-C ISI-0272-C ISI-0410-C VT-2 UT a PT Instrumentation Noz Noz"SE Wld 2 4" R;WWQS146G

RBV 0008 2-SI"4.6.G Page 66 SECTION 8.1 EXAMINATIONSCHEDULE PART 1 - CLASS 1 EQUIVALENT (IWB) COMPONENTS (Continued)

Examination Item Category No.

B-F B5.20 Number of Components Second Inspection System/

Interval Subtotal Sample First Period Sample Second Third Period Period Sample Sample Components Shown On Exam(s)

ISI Drawing I Required Remarks Refer to Section 7.3.1.D B-F B-F B5.30 N/A B5.130 9

Cs/8 RHR/1 N/A ISI-0271-C ISI-0221-C Hone UT a Dissrm Pape Wld PT

~)

4

'-F B5.140 Refer to Section 7.3.1.D B-F B-G-1 B-G-1 B-G-1 B5.150 B6.10 B6.20 B6.30 92 92 92 RPV RPV RPV 92 92 4 (i2) 92 (if studs removed) 22 22 35 35 35 35 4 (i2)

ISI-0266-C ISI-0266-C ISI-0266"C UT(42)

MT UT(*2)

Clos Hd Nuts Studs (In Place)

Studs (When Removed)

Refer to Section 7.3.1.D B-G-1 B6.40 92 RPV 92 22 35 35 ISI"0266-C Threads (When Head Removed)

R.'WVlh2SI46G

. ~

2-SI-4.6.G Page 67 SECTION 8.1 EXAMINATION SCHEDULE PART 1 - CLASS 1 EQUIVALENT (IWB) COMPONENTS (Continued)

Examination Item Category No.

B-G-1 B6.50 Number of Components 92 sets Second Inspection System/

Interval Subtotal Sample 92 sets First Period Sample 22 sets Second Period Sample 35 sets Third Period Sample 35 sets Components Shown On ISI Drawing 8

ISI-0266-C Exam(s)

Required Remarks Washer (Sets of 2)

B-G-1 B6. 50 RPY 92 22

.35 ISI-0266-C Bushing~

(Whe Head Removed)

B-G-1 B-G-1 B-G-1 B-G-1 B-G-1 B-G-1 B-G-2 B-G-2 B-G-2 B6. 150 N/A B6.180 32 B6.190 2

86.200 32 86.200 32 86.210 N/A B7. 10 N/A 87.50 17 B7.60 N/A RECIR RECIR RECIR RECIR MS/12 RECIR/2 RPV/3 N/A 16 (~3) 1('3) 16(i3) 16 (43)

N/A N/A 17 12 2

3 N/A 1('3) 16 16 16 ISI-0407-C ISI-0407-C ISI-0407-C ISI-0407-C ISI-0312-B ISI-0270-C ISI-0408-C UT VT-1 VT-1 VT-1 None Recir Pump Bolting Flange Face Recir Pump Nuts Recir Pump Washers Hone None Pipe Bolting S 2" Bolting to RPV Hd Nor None RWWQS(46G

RBV OOOS 2-SI-4.6.G Page 68 SECTION 8.1 EXAMINATIONSCHEDULE PART 1 CLASS 1 EQUIVALENT (IWB) COMPONENTS (Continued)

Examination Item Category No.

Number of Components Second Inspection System/

Interval Subtotal Sample First Period Sample Second Period Sample Third Period Sample Components Shown On ISI Drawing I Exam(s)

Required Remarks B-G-2 B-G-2 B-H B-J B7.70 B7.80 B8.10 185 B9.11 389 cs/4 FW/6 HPCI/1 MS/8 MS/13 RECIR/6 RHR/5 RWCU/3 RPV RPV CS/23 FW/76 HPCI/20 MS/120 RCIC/6 RECIR/78 RHR/35 RPY/13 RWCU/18 15 (~10) 2 (~10) 2 (~10) 1 (~10) 1 (ilo) 1 (ilo) 3 (~10) 3 (~10) 2 (~10) 185(*4) 100 (~6) 5 18 5

26 2

17 8

13 45(~4) 29

-"('4) 1(i5) 36 10 9

10 1

4

(*4) 1(45) 35 7

ll 5

7 5

ISI-0271-C ISI-0269-C ISI-0273-C ISI-0222-C ISI-0312-B ISI-0270-C ISI-0221-C ISI-0272-C ISI-0292-C ISI-0415-C ISI-0271-C ISI-0269-C ISI-0273-C ISI-0222-C ISI-0272-C ISI-0270-C IS I-0221-C ISI-0222-C 4

ISI-0269-C C

ISI-04O8-C ISI-0272-C i VT-1 PT or UT ST C UT MT 6 UT MT a UT MTCUT MT a UT MTaUT PT a

UT PT a

UT MT a UT PT a UT Valve Bolting 5 2" See Section 8.3 FCV-1-??

PCV-1-???

CRD Housing Bolts RPV IA's RFR-ISI-2-1 Circumferential Welds 2 4" RPV Nox-SE Allo Steel Welds (Not Dism Metal)

RWWQSh6G

REV 0008 2-SI-4.6.G Page 69 Second SECTION 8.1 EXAHINATION SCHEDULE PART 1 CLASS 1 EQUIVALENT (IWB) COMPONENTS {Continued)

Inspection Examination Item Number of Syst: em/

Interval Category No.

Components Subtotal Sample B-J B9.12 Note 7 First Period Sample Second Period Sample Third Period Sample Components Shown On Exam(s)

ISI Drawing I Required Remarks ST 4 UT Longitudinal Welds 2 4" B-J B9.21 Refer to Section 7.3.1.D B-J B-J B9.22 N/A B9.31 42 MS/26 RECIR/15 RHR/1 N/A ISI-0222-C ISI-0270"C ISI-0221-C ST a UT MT a UT PT c UT PT C UT None Branch Connections 2 4" B-J B9.32 Refer to Section 7.3.1.D RKWQSI46G

REV 0008 2-SI-4.6.G Page 70 SECTION 8.1 EXAMINATIONSCHEDULE PART 1 - CIASS 1 EQUIVALENT (IWB) COMPONENTS (Continued)

Examination Item Category No.

Number of Components second Inspection System/

Interval Subtotal Sample Pirst Period Sample Second Third Period Period Sample Sample Components Shoun On Exam(s)

ISI DraMing I Required Remarks B-J B9.40 Refer to Section 7.3.1.D B-K-a B10.10 54 Cs/5 EW/10 HPCI/1 MS/17 RECIR/18 RHR/3 5

10 1

17 18 3

10 1

18 17 1

22 17 ISI-0280-C ISI-0277-C ISI-0275-C ISI-0279-C ISI-0278-C ISI-0276-C Piping Integral Attachments (IA's) 2 5/8" RFR ISI-2-7 B-K-1 B-K-1 B K-1 B-L-1 B L-2 B10.20 6

B10 ~ 30 2

N/A B12. 10 N/A B12.20 2

RECIR RECIR N/A N/A 1(i8)

ISI-0278-C ISI-0277-C ISI"0407-C PT Pump IA's 2 5/8" Valve IA k 5/8" Class 1 IA < 5/8" None Pump Casing Interior R LRWQSI46G

2-SI-4.6.G Page 71 SECTION 8.1 EXAMINATIONSCHEDULE PART 1 CLASS 1 EQUIVALENT (IWB) COMPONENTS (Continued)

Examination Category B-M-1 B-M-1 B-M-2 Item No.

B12.30 B12.40 B12.50 Number of Components N/A N/A Second Inspection System/

Interval Subtotal Sample N/A N/A 21 (~9)

First Period Sample Second Period Sample Third Period Sample 13(e9)

- Components Shown On ISI Drawing 8

Exam(s)

Required VT"3 Remarks None None Valve Body >>

See Section 8.3.

B-N-1 B-N-2 B13.10 B13.20 cs/6 FW/6 HPCI/3 MS/21 RCIC/1 RECIR/6 RHR/9 RWCU/3 3 (~10) 2 (~10) 2 (~10) 2 (410) 1 (410) 3 (il0) 6 (i10) 2 (~10)

ISI-0271-C ISI-0269-C ISI-0273-C ISI"0222-C ISI-0272-C ISI-0270-C ISI-0221"C ISI-0272-C CHM-2046-C CHM-2046-C VT-3 VT-1 RPV Interior RPV Interior Att in Beltline Region B-N"2 B13.30 B-N-2 B13 ~ 40 RPV RPV CHM-2046-C CHM-2046-C RPV Interior Att Beyond Beltline Region Shroud Supp Surfaces B-0 B-P B14. 10 40 RPV

--See Section 7.9 and SSP-8.5 ISI-0292"C VT-2 CRD Housing weld Pressure Test Program R:lBWQS(46G

2-SI-4. 6.G Page 72 SECTION 8.1 EXAMINATIONSCHEDULE PART 1 - CLASS 1 EQUIVALENT (IWB)

COMPONENTS (Continued)

NOTES:

('1)

Bolting replaced in cycle 6 refueling outage.

Preservice examination performed on all 32 sets of bolting.

(~2)

Studs (Bolting) may be examined in place under tension (B6.20),

when connection is disassembled (B6.20, or when the bolting is removed (B6.30). Studs shall be surface examined only if removed.

The four studs normally removed for refueling have been scheduled under Item Number B6.30. Others shall receive a surface exam if removed in accordance with Table IWB-2500-1, Examination Category B-G-1, NOTE:

(1).

( ~ 3)

Examine bolting of only one pump in accordance with Table IWB-2500-1, B-G-1, NOTE:

(3) in con)unction with B-L-2, NOTES (1)

~

( 4)

Bolts, studs, and nuts in CRD Housing examined only when disassembled in accordance with Table IWB-2500-1, Examination Category B-G-2, Extent and Frequency of Examination.

(~5)

UT accessible length of RPV-SUPPORT-IA, approximately half 2nd period and half 3rd period.

(~6)

Approximately 90% of the B-J welds, within practical limits of accessibility, shall be examined during the life of the plant. All carbon steel or low alloy (similar metal)

RPV noxrle-to-safe end welds plus additional welds to comprise a

25%

sample shall be examined each interval. All dissimilar metal welds are examined under Examination Category B-F.

('7) class 1 longitudinal welds shall be examined when they intersect a circumferential weld selected for examination.

The examination of longitudinal welds is in accordance with the alternative specified in code case N-524.

(+8)

Examine only one pump in accordance with Table 2500-1, B-L-2, NOTE:

(1) 6 (2). This examination shall be performed during Cycle 6 in accordance with the NRC SER for Relief Request ISI-4 (letter A02 891030 018) associated with the first inspection interval.

(~9)

Examine only one valve per Group in accordance with Table 2500-1, B-M-2, NOTE: (3). There are 21 Groups of Class 1 valves NPS 4 or larger.

(+10) Number of Groups of CLass 1 valves exceeding NPS 4 contained wi.thin this system (Examination Category and/or Item Number).

R WVA2SI46G

0

~

~

L

~ I,

~

RBV0008 2-SI-4.6.6 Page 73 SECTION 8.1 EXAMINATIONSCHEDULE PART 2 - CLASS 2 E0UIYALENT (IWC)

COMPONENTS Examination Item Category No.

C1.10 C1.20 Number of Components 12 Second Inspection System/

Interval Subtotal Sample 3 ('1)

First Period Sample Second Period Sample Third Period Sample Components Shown On ISI Drawing I ISI-0406-C ISI-0406-C Exam(s)

Required UT Remarks RHRHX RHRG-2-07 Shell RHRG-2-08 Cir RHRG-2-09 Hea RHRHX C-A C-B C-B C-B C-B C-B C-B C-C C-C C2.22 N/A C2.31 16 C2.32 N/A C2.33 8

C3. 10 12 C3.20 46 C1.30 N/A C2. 10 N/A C2.21 4

cs/6 HPCI/4 Ms/8 RHR/28 N/A N/A I('2)

N/A 4 (42)

N/A 2 (i2) 3 (i3) 6 4

8 28 10 20 4

12 16 16 ISI-0406-C None ISI-0406-C ISI-0406-C ISI-0406-C ISI"0105-C ISI-0130-C ISI-0079-C ISI-0324-C UTaMT RHRG-2-10 Circ.

None None RHRHX RHRG-2-11 Head Nor Weld.

RHRHX RHRG-2-05A Nor Rein RHRG-2-i:B forcing RHRG-2-06A Plate RHRG-2-06B Welds.

None RHRHX RHRG-2-05 4 -06, Nor Reinforcino Pit relief "tellt hole 8 Press Pres Yes IA's

-> 3/4" RHRHX Piping IA's

> 3/4" RWWQSI46G

REV 0008 2-SI-4.6.G Page 74 SECTION 8.1 EXAMINATIONSCHEDULE PART 2 - CLASS 2 E UIVALENT INC COMPONENTS Second Inspection Examination Item Number of System/

Interval

~Cate or No.

Co onente Subtotal S

le First Second Third Components Period Period Period Shown On S

le san le

~san Ie Zsr Srauin S

Exam(s)

Re ired Remarks C-C C-C C-C C-D C-F-1 C3.30 C3.40 NIA C5.11 4

NIA 98 N/A 13 CS/6 HeCT/5 RHR/2 4

N/A N/A N/A 13 2

2 ISI-0310-B ISI-0103-C IS I-0128-C MSG-0018-C PT 4 UT Pump IA's None CLASS 2 IA's None Dissim metal circ welds 3/8" nom.

3/4"

<3'"

C Ss 4"

c wall.

C-F-1 C5.12 Note 4

PT a

UT Dissim metal a ss long welds

> 4" a

tb> 3/8"nom. wall.

C-F-1 C-F-1 C-F-1 C F-2 C5.20 N/A C5.30 N/A CS. 40 N/A N/A 151 (i6)

N/A N/A NIA N/A CS/21 N/A RBCCW/16 NIA RCIC/38 N/A RHR/76 N/A ISI"0103-C ISI-0031-C ISI-0129-C MSG-0018-C NIA BWR Plant None None

< 3/8" nom. wall Excluded See Section 7.3.4.8 R;PLVA2SI46G

RBV0008 SECTION 8.1 EXAMINATIONSCHEDULE pART 2 - cUlss 2

E uzvALENT znc coMpoNENTs 2-SI-4.6.G Page 75 C"F-2 C5.51 935 (1086) (~5)

CRD/72 CS/144 HPCI/156 MS/114 RCIC/43 RHR/406 6

12 14 10 6

36 Second Inspection Examination Item Number of System/

Interval

~Cats or No.

Co onsnts Subtotal S

ls First Period Sam le 26 6

7 10 3

Second Period Sam le 30 3

20 Third Period

~Saln ls 28 12 16 Components Shown On ISI Drawin 8

ISI-0040-C

'SI-0103-C ISI-0128-C MSG-0021-C ISI-0129-C MSG-0018-C Exam(s)

Re uired Remarks MT a

CS Circ Welds

> 4" UT a

aa> 3/8" nom. wall.

Includes containment heat removal.

C-F-2 C5.52 Note 4

MT a

CS Long Welds

> 4" UT a

aa> 3/8" nom. wall.

C-F-2 C-F-2 C-F-2 C5.60 N/A C5.70 N/A C5.81 5

RHR/3 cs/1 MS/1 N/A N/A MSG"0018-C ISI-0103-C MSG-0021-C BWR Plant None MT Sweep-o-let branch connection C"G C6. 10 N/A C-G C6.20 N/A C-H ALL Pressure Test Program.

N/A

--See Section 7.9 and SSP-8.5.

None None RMWQS(46G

0 REV 0008 SECTION 8.1 EXAMINATION SCHEDULE PENT 2 - CENSE 2 EQNZVEEENT TNC COMPONENTS 2-SI-4

~ 6PG Page 76 NOTES

(~1)

Examinations limited to one vessel of similar design, size, function in accordance with Table.IWc-2500-1, Examination Category C-A, NOTE: (3).

(~2)

Examinations limited to one vessel of similar design,

size, function in accordance with Table IWC-2500-1, Examination Category C-B, NOTE: (4).

(~3)

Examinations limited to one vessel of similar design,

size, function in accordance with Table IWC-2500-1, Examination Category C-C, NOTE: (2).

(~4) class 2 longitudinal welds vill be examined vhen they intersect a circumferential weld selected for examination.

The examination of longitudinal velds is in accordance with the alternative specified in coda case N-524.

(*5)

Total count (1087) of Item Numbers C5.51 (circumferential welds )

3/8" nominal wall) a Item Numbers N/A (excluded velds due to thickness being

< 3/8" nominal vali) to which the 7.5

% sampling rate is applied to arrive at 82 welds to be examined.

The second interval sample is prorated to each system by using the ratio of the nonexempt C-F-2 welds for the system to the total of C-P-2 circumferential welds. (i.e. For RHR:

(74 + 406)/1095 X 82 36).

See Table IWC-2500-1, C-F-2P NOTES:

(2)

(~6)

Item Numbers N/A are the circumferential welds ( 3/8" nominal wall. There are 151 of these welds and they are included here to establish a total veld count.

They are not sub)ect to examination.

see section 7.3.4.B.

RPLWQSl46G

REV 0008 SECTION 8.1 EXAMINATIONSCHEDULE PART 3 - CLASS 3 E VIVALENT IWD COMPONENTS 2"SI-4.6eG Page

.7

,Second Inspection Examination Item Number of System/

Interval

~cate os No.

Co onants subtotal s

le First Period Sam le Second Third Period Period san le

~san le Components Shown On ISI Drawin I

Exam(s)

Re ired Remarks D-A D-B N/A D2.10 N/A

-- See Section 7.9 and SSP-8.5.--

None Pressure Test Program.

D-B D2.20 94 EECW/74 74 RCW/2 2

RHRSW/18 18 31 12 1

18 31 31 32 31 1

ISI-0368-C ISI-0391"C ISI-0145-C VT-3 IA's Comp Supports t Restraints.

D-B D2.30 15 MS 15 ISI-0412-C IA's ON SNUBBERS.

D-B D2.40 35 MS/26 RHRSW/9 35 26 9

12 12 12 12 ISI-0412-C ISI-0145-C IA's Spring Type Piping Comp Supports'LNWQSI46Q

REV 0008 2-SI-4.6aG Page 78 SECTION 8.1 EXAMINATIONSCHEDULE PART 3 - CLASS 3 E UIVALENT IWD COMPONENTS Examination C~aaa as D-B D-B D-C Item No.

D2.SO D2.60 D3.10 Number oE Co onents N/A N/A Second Inspection System/

Interval Subtotal S

le N/A N/A First Period S

le Second Third Period Period s

la

~sam la

-- See Section 7a9 and SSP-8.5.

Components Shorn On ISI DraMin Exam(s)

Re ired Remarks None None Pressure Test Program.

D-C D3.20 FPC ISI-0133"C VT-3 IA's on Comp Supports a

Restraints.

D-C D3.30 N/A thru D3.60 N/A None RLBVIA2cr46G

RBV0008 SECTION 8.1 EXAMINATIONSCHEDULE PART 4 - COMPONENT SUPPORTS IWF CODE CASE N-491 2-SI-4

~ 6. G Page 79 Examination Item

~tate ot No.

Number of Co onents Second Inspection System/

Interval Subtotal S

le First Period S

le Second Period sam le Third Period

~ao t Components Shown On ISI Drawin Exam(s)

Re ired Remarks Fl.10 139 40 14 13 13 VT-3 CLASS 1 PIPE SUPPORTS.

SUBTOTALS FOLLOW BELOW.

F-A F1. 10A 6

MS/5 RECIR/1 ISI-0279-C ISI-0278-C ONE DIRECTIONAL RIGID SUPPORTS F-A F1.10B 18 FW/4 HPCI/1 MS/5 RECIR/2 RHR/2 RWCU/2 CS/2 ISI-0277-C ISI-0275-C ISI-0279-C ISI-0278-C ISI-0276-C ISI-0274-C ISI-0280-C VT-3 MULTIDIRECTIONAL RIGID SUPPORTS.

RWVA2SI46G

REV 0008 SECTION 8.1 EXAMINATIONSCHEDULE PART 4 COMPONENT SUPPORTS IWF CODE CASE N-491) 2-SI-4.6.G Page 80 Examination Item catalaCor t

No.

Number of Co onents Second Inspection System/

Interval Subtotal S

le First Period S

le Second Period S

le Third Period

~Sala le Components Shown On ISI Drawin 4

Exam(s)

Re uired Remarks F-A F1.10C 115 CS/10 FW/29 HPCI/3 MS/36 RECIR/22 RHR/13 RWCU/2 31 3

8 1

10 5

3 1

ISI-0280"C ISI-0277-C ISI-0275-C ISI-0279-C ISI-0278-C ISI-0276-C ISI-0274-C VT-3 VARIABLE SUPPORTS.

(SNUBBERS, CONSTANT FORCEPS

SPRINGS, ETC.)

F-A Fl.20 336 51 15 17 19 CLASS 2 PIPE SUPPORTS.

SUBTOTALS FOLLOW BELOW.

RMWQSl46G

P 1

REV 0008 SECTION 8.1 EXAMINATIONSCHEDULE PART 4

COMPONENT SUPPORTS IWF CODE CASE N-491 2-SI-4.6.G Page 81 Examination Item Number of cats>sonar no.

co onsnts s

F-A F1. 20A 107 Second Inspection System/

Interval Subtotal S

le 17 First Period S

le Second Period Sam le Third Period

~sas t*

Components Shown On ISI Drawin

¹ Exam(s)

Re uired Remarks VT-3 ONE DIRECTIONAL RIGID SUPPORTS F-A F1.20B 65 F-A F1.20C 158 CRD/14 CS/16 HPCI/25 RBCCÃ/2 RCIC/11 RHR/39 CRD/13 CS/8 HPCI/7 MS/6 RCIC/4 RHR/27 cs/13 HPCI/20 MS/31 RCIC/8 RBCCW/1 RHR/85 2

2 1

2 6

10 3

3 4

1 1

12 ISI-0041-C ISI-0105-C ISI-0130-C ISI-0032-C ISI-0131-C ISI-0324-C ISI-0041-C ISI-0105-C ISI-0130-C ISI-0079-C ISI-0131-C ISI-0324-C ISI-0105-C ISI-0130-C ISI-0079-C ISI-0131-C ISI-0032-C ISI-0324-C VT-3 MULTIDIREC IONAL RIGID SUPPORTS VT-3 VARIABLE SUPPORTS.

(SNUBBERS s CONSTANT

FORCE, SPRINGS, ETC. I F-A Fl.30 450 13 18 17 VT-3 CLASS 3 PIPE SUPPORTS.

SUBTOTALS FOLLOW BELOW.

R:WVA2SI46G

RBV0008 SECTION 8.1 EXAMINATIONSCHEDULE PART

~ - COMPONENT SUPPORTS SNP CODE CASE N-491 2-SI-4 '.G Page 82 Examination Item Catalaor No.

Number of Co onents Second Inspection System/

Interval Subtotal S

le First Period S

le second Period S

le Third Period Sam~le Components Shown On ISI Drawin I

Exam ts)

Re ired Remarks F-A F1.30A 116 F-A Fl.30B 268 F-A Fl. 30C 66 EECW/85 FPC/1 MS/1 Rcw/4 RHRSW/25 EECW/180 FPC/4 MS/53 RCW/5 RHRSW/26 EECW/3 MS/54 RHRSW/9 13 28 18 1

6 1

2 10 ISI-0368-C ISI-0133-C ISI"0412-C ISI-0391-C ISI-0145-C ISI"0368-C ISI-0133-C ISI-0412"C ISI-0391-C ISI-0145-C ISI-0368-C ISI-0412-C ISI-0145-C VT-3 ONE DIRECTIONAL RIGID SUPPORTS VT-3 MULTIDIRECTIONAL RIGID SUPPORTS.

VT-3 VARIABLE SUPPORTS.

lSNUBBERSP CONSTANT

FORCE, SPRINGS, ETC.)

R:lBWQSI46G

~

~

RLsV 0008 SECTION 8-1 EXAMINATIONSCHEDULE PART 4

COMPONENT SUPPORTS IWF CODE CASE N-491 2"SI"4.6.G Page 83 Examination Item

~cate ot No.

F-A Fl.40 Number of Co onents Second Inspection System/

Interval Subtotal S

le 33 First Second Period Period Sam le Sam le ll ll Third Period

~Sun t Components Shown On ISI Drawin I

Exam(s)

Re ired Remarks ALL CLASSES Or COMPONENT SUPPORTS (NOT PIPE SUPPORTS).

SUBTOTALS FOL BELOW.

F-A Fl.40A 1

RCIC/1 ISI-0131-C F-A Fl.40B 48 F-A F1.40C 25 NOTE:

CRD/6 cs/4 EECW/16 HPCI/3 RCIC/2 RHR/12 RHR/4 RPV/1 FW/2 RECIR/2 RECIR/18 RHR/2 RPV/1 16(*1) 3 (*1) 1(41) 2 (il) 16 (*1) 2 2

9(ii) 2 1

ISI-0041-C ISI-0105-C ISI-0368"C ISI-0130-C ISI-0131-C ISI-0406-C ISI"310-B ISI-0415-A ISI-0277-C ISI-0278-C ISI-0278-C ISI-0324-C ISI-0415-C VT-3 VT-3 VT-3 VT-3 VT-3 MULTIDIRECTIONAL RIGID SUPPORTS.

TANK SUPPORTS.

PUMP SUPPORTS.

PUMP C STRAINER SUPPORTS.

TURBINE a PUMP SUPPORTS.

TURBINE i PUHP SUPPORTS.

RHR HX SUPPORTS'HR PUMP SUPPORTS RPV SUPPORT.

VALVE SUPPOR't VALVE SUPPORTS RECIR PUMP SUPPORTS VALVE SUPPORTS RPV STABILIZER (i1)

For multiple components other than piping, within a system of similar design,

function, and service, the supports of only one of the multiple components are required to be examined.

See Table -2500-1, Examination Category F-A, Notes (3).

R:PLVA2SI46G

SECTION 8.1 EXAMINATIONSCHEDULE PART 5 - AUGMENTED EXAMINATIONS(~1) 2-SI-4.6.G Page 84 Augmented Exam Cate or Ref.

Program Section Exam Regmt Refueling Refueling Refueling Refueling Refueling Number of Source Cycle 6

Cycle 7 Cycle 8

Cycle 9

Cycle 10 Co onents Code Sam le S

le S

le Sam le S

le Refueling Cycle 11 Sam le Exams Re ired Remarks 7.12.8 42 B02-02 6(12%) in 6 years--

--ll(25%)

in 10 years UT Section 8.2 NUREG-0313 7.12.8 120 7.12.8 7

B02-02 B02-02 121 12 6

-60(501) in 6 years

-120(100%)

in 10 years UT Section

~

NUREG-0 Section 8.2 NUREG-0313 7.12.8 16 7.12.8 2

B-D 7.12.7 6

NA(~2) 7.12.8 15 B02-02 9

B02-02 8

B02-02 B01-02 N/A Section 8.2 NUREG-0313 Section 8.2 NUREG-0313 stainless Welds,Temp.

Exclusion NUREG-0313 NUREG-0619 Feedwater,

Nozzle, Bore C

SE B-J 7.12.6 3

B01-02 3

NUREG-06' Welds a

CRD Rerou'te B-N-1 7.12.7 6

7.12. 6 1

B01"02 B01-02 1

VT-I UT NUREG-0619 FN Nozzles Spargers.

NUREG-0619 Base metal at CRD Reroute.

RP1%QSl46G 1

RBV0008

):

2"SI-4.6.G Page 85 SECTION 8.1 EXAMINATIONSCHEDULE PART 5

- ADENENTED EEANENATZDNE( 1)

Augmented Exam Cate or Rei.

Program Section Exam Reqmt Refueling Refueling Number of Source Cycle 6

Cycle 7 Co onents Code S

le S

le Refueling Refueling Refueling Refueling Cycle 8

Cycle 9

Cycle 10 Cycle ll Exam(s)

S le Sam le Sam le Sam le Re uired Remarks B-N-1 B-J B-A B-N-1 7.12.11.1 2

7.12 '

31 7.12.10 21 7.12.1 1

7.12.2 1

7.12.3 4

B06-02 B04-02 BOS-02 D01-02 D02-02 D03-02 21 11 UT UT UTCRT VT-1 UT IEB 80-13 CS Spargers Tech

'.6.G.2 Pipe Whip RPV Welds NOTES:

(il)

Most of these components are considered within the Code examination numbers presented in Parts 1 through 4 of this Section.

Where one examination may serve as Code credit and as Augmented credit, it shall be so credited.

(i2)

These stainless steel welds contain coolant at a temperature of 200 degrees or less during power operation and do not require examination under NUREG-0313.

These welds are listed in Section 8.2, Part 2.

R:WWQS)46G

SECTION 8.2 - PART 1

UNIT 2 WELDS REQUIRED TO BE EXAMINED PER GENERIC LETTER 88-01 2-SI-4.6.G Page 86 WELD NUMBER 2RA5 2RA6 2RBS 2RB6 2RCS 2RC6 2RDS 2RD6 2RES 2RE6 2RFS 2RF6 2RGS 2RG6 2RHS 2RH6 2RJS 2RJ6 2RKS 2RK6 2RAl 2RB1 2RC1 2RDl 2REl 2RF1 2RG1 2RH1 2RJ1 2RK1 JP-2-1A JP-2-1B DRWC-2-07A DRWC-2"07B RWC-2-001-G001 RWC-2-001-G002 RWCU-2-003-G001 RWCU-2-003-G002 RWCU-2-003-G003 RWCU-2-003-G004 RWCU-2-004-G073 RWCU-2-004-G074 SYSTEM RECIR RECZR RECZR RECIR RECIR RECIR RECIR RECZR RECZR RECIR RECZR RECIR RECZR RECZR RECZR RECIR RECIR RECZR RECIR RECZR RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RWCU RWCU RWCU RWCU RWCU RWCU RWCU RWCU RWCU RWCU EXAM METHOD UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT PIPE SIZE (INCHES) 12 12 12 12 12 12 12 12 12 12 12 12 12

'2 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 4

6 6

4 4

6 6

6 6

4 4

WELD CONFIG P,P P,SE P,P P,SE P,P POSE P,P P,SE P,P Pi SE P,P P,SE P,P P,SE P,P P,SE P,P P,SE P,P POSE N,SE N,SE N,SE NiSE N,SE Np SE N,SE NiSE N,SE N,SE NiSE N,SE P,P P,P V,V E,V EiP E,P PEN, P P,V P,V PiV ZGSCC EXAM CATEGORY A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A RLHWQSI46G

2-SI-4 '.G Page 87 SECTION 8.2 PART 1

UNIT 2 WELDS REQUIRED TO BE EXAMINED PER GENERIC LETTER 88-01 WELD IIUNBER SYSTEM EXAM METHOD PIPE SIZE (INCHES)

WELD CONFZG IGSCC EXAM CATEGORY DCS-2-04 DCS-2-05 DCS-2-07 DCS-2-13 DCS-2-13A DCS-2-14 DSCS-2-01 DSCS-2-02 DSCS-2-09 TCS-2-403 TCS-2-405 TCS-2-406 TCS-2-410 TCS-2-422 TCS-2-426 TSCS-2-418 GR-2-01 GR-2-02 GR-2-03 GR-2-04 GR-2-07 GR-2-08 GR-2-09 GR-2-12 GR-2-18 GR-2-19 GR-2-22 GR-2-25 GR-2-26 GR-2-27 GR-2-28 GR-2-29 GR-2-30 GR-2-33 GR-2-34 GR-2-35 GR-2-38 GR-2-41 GR-2-44 GR-2-48 GR-2-51 CS CS CS CS CS, CS CS CS CS CS CS CS CS CS CS CS RECZR RECZR RECIR RECIR RECIR RECIR RECZR RECIR RECZR RECZR RECIR RECZR RECIR RECIR RECZR RECIR RECZR RECIR RECIR RECZR RECIR RECIR RECIR RECIR RECZR UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT 12 12 12 12 12 12 12 12 12 10 12 12 12 12 12 10 28 28 28 4

28 12 12 22 12 12 22 22 28 28 28 4

28 12 12 12 22 12 22 P,P P,V P,P P,P P,P P,V E,P E,P P,P P,SE EiV P,V E,V P,V E,P P,SE P, PMP P,V E,V Ci p C,P T,X PgP P,P H,X P,P P,P H,V H,V Pg PMP P,V E,V C,P C,P P,X P,P P,P P,R H,X P,P H,V C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

RWWQSI46G

SECTION 8.2 - PART 1

UNIT 2 WELDS REQUIRED TO BE EXAMINED PER GENERIC LETTER 88-01 2-SI"4.6.G Page 88 WELD HDMSER SYSTEM EXAM METHDD P1PE SIZE tINCHES)

WELD COHTZH IGSCC EXAH CATEGORY GR-2-52 GR-2"54 GR-2-55 GR-2-56 GR-2-57 GR-2-58 GR-2-60 GR-2-62 GR-2-63 GR"2-63A GR-2-63B KR-2-01 KR-2-02 KR-2-03 KR-2-04 KR-2-11 KR-2-12 KR-2-13 KR-2-15 KR-2-19 KR-2-20 KR-2-23 KR-2-24 KR-2-25 KR"2"26 KR-2-33 KR-2-34 KR-2-35 KR-2-42 KR-2-45 KR-2-46 KR-2-47 KR-2-48 KR"2-49 KR-2-50 KR-2"51 KR-2-52 KR-2-53 RECIR RECIR RECZR RECIR RECZR RECZR RECZR RECIR RECZR RECZR RECZR RECZR RECIR RECZR RECZR RECZR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECZR RECZR RECIR RECIR RECZR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT 22 28 28 28 28 28 28 28 28 4

28 28 22 22 12 22 12 12 4

28 28 22 22 12 12 28 28 28 28 4

28 28 28 H,V E,P P,T E,V P,V E, PMP E,P E,V P,V F,F BC BC E,P P,T BC R,X H,X BC C,H BC BC BC E,P P,T BC R,X H,X BC BC E,P P,T EEP EEP BC E,P E,P EEP BC C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C RWWQSI46G

REV 0008 2-SZ-4.6.G Page 89 SECTION 8.2 -

PART 1

UNIT 2 WELDS REQUIRED TO BE EXAMINED PER GENERIC LETTER 88-01 WELD NUMBER SYSTEM EXAM METHOD PIPE SIZE tZNCHES)

WELD CONFZG IGSCC EXAM CATEGORY DRHR-2-02 DRHR-2-04 DRHR-2<<0S DRHR-2-06 DRHR-2-07 DRHR-2-08 DRHR-2-13 DRHR-2-14 DRHR-2-15 DRHR-2-16 DRHR-2-17 DRHR-2-18 DRHR-2-19 DRHR-2-21 DRHR-2-23 DSRHR-2-01 DSRHR-2-02 DSRHR-2-03 DSRHR-2-04 DSRHR-2-04A DSRHR-2-05 DSRHR-2-OSA DSRHR-2-06 DSRHR-2-07 DSRHR-2-08 DSRHR-2-09 DSRHR-2-10 DSRHR-2-11 TRHR-2-191 N 1A-SE N 1B-SE TCS-2-401 TCS-2-417 DRWC-2-01 DRWC-2-OIA DRWC-2-02 DRWC-2-03 DSRWC-2-01 RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RPV RPV RPV RPV RWCU RWCU RWCU RWCU RWCU UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT 24 24 24 24 24 24 24 24 24 24 24 24 20 20 20 24 24 24 24 24 24 24 24 24 6

20 20 20 20 28 28 10 10 6

6 6

6 6

P,V E,P PiV P,V P,V P,V E,P E,V P,V EiV P~V P,T P,T E,V P,V E,P P,P P,P E,P E~P E,P EgP P,P E,P BC E,P E,P E,P E,V N,SE N,SE N~SE N,SE P,V PiV EgV P,V E,P C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C C

C R:WWQSI46G

REV 0008 2-SZ-4.6.G Page 90 SECTION 8.2 PART 1

UNIT 2 WELDS REQUIRED TO BE EXAMINED PER GEN-RIC LETTER 88-01 WELD" NUMBER SYSTEM EXAM METHOD PIPE SIZE (INCHES)

WELD CONFEG IGSCC EXAM CATEGORY DSRWC-2-01A DSRWC-2-02 DSRWC-2-06 RCRD-2-49 RCRD-2-50 RCRD-2-52 DRHR-2-03 DRHR-2-11 DRHR-2-3.2 RCRD-2-33 TCS-2-421(OL)

GR-2-15(OL)

GR-2-45(OL)

GR-2-53 GR-2-59(OL)

GR-2-61(OL)

GR-2-64 (OL)

KR-2-14 KR-2-36 KR-2"37 KR-2-41 DRHR-2-09 DRHR"2-22 DSRWC-2-03(OL)

DSRWC-2-04(OL)

DSRWC-2-05(OL)

DRHR-2-03B DRHR-2-13B RWCU RWCU RWCU CRD CRD CRD RHR RHR RHR RPV CS RECZR RECZR RECZR RECZR RECZR RECZR RECIR RECZR RECIR RECIR RHR RHR RWCU RWCU RWCU RHR RHR UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT VT-2 VT-2 6

6 6

4 4

4 24 24 24 4

12 12 12 28 28 28 28 12 12 22 12 24 20 6

6 6

24 24 E,P E,P E,P E,V E,V P,V P,V P,V P,V O',N EEV P,R P,P P,SE P,SE P,P E, PMP BC BC CEH BC P,T P,V E,P E,P E,P P,P P,P C

C C

D D

D D

D D

D E

E E

E E

E E

E E

E E

E E

E E

E.

G G

RRWQSI46G

REV 0008 2-SI-4.6.G Page 91 SECTIO"'.2 -

PART 2 UNIT 2 STAINLESS AND DISSIMILAR METAL WELDS NOT SUBJECT TO GENERIC LETTER 88-01 EXAMS WELD NUMBER PIPE SIZE WELD SYSTEM (INCHES)

CONFIG ZGSCC EXAM CATEGORY METHOD COMMENTS DCS-2-01 DCS-2-02 DCS-2-03 DCS-2-10 DCS-2-11 DCS-2-12 DSCS-2-14 DSCS-2-15 CS 12 CS 12 CS 12 CS 12 CS 12 CS 12 CS 12 CS 12 P,V E,V PiV E,V PiV P,V E,P E,P NA NA NA NA N/A TEMPERATURE EXCLUSION N/A TEMPERATURE EXCLUSION N/A TEMPERATURE EXCLUSION N/A TEMPERATURE EXCLUSION N/A TEMPERATURE EXCLUSION N/A TEMPERATURE EXCLUSION N/A TEMPERATURE EXCLUSION N/A TEMPERATURE EXCLUSION DSCS-2-16A CS 12 P, PEN N/A INACCESSIBLE ZN PENETRATION X-16A.

TEMPERATURE EXCLUSION.

DSCS-2-16B CS 12 P, PEN NA N/A INACCESSIBLE ZN PENETRATION X-16A.

TEMPERATURE EXCLUSZON.

SHPCZ-2-1 HPCI SHPCI-2-2 HPCI SHPCI-2-3 HPCZ SHPCZ-2-4 HPCI SHPCZ-2-5 HPCI 12 12 12 12 12 E,P E,P E,P E,P N/A TEMPERATURE EXCLUSION N/A TEMPERATURE EXCLUSION N/A TEMPERATURE EXCLUSION N/A TEMPERATURE EXCLUSION N!A TEMPERATURE EXCLUSION

~

t; L.

RWVA2SI46G

RHV0008 SECTION 8.3 ASME CLASS 1

E UIVALENT VALVE LIST 2-SI-4.6.G Page 92 GROUP RIM!DR VALVE NUMBER 3-554 3-558 3-568 3-572 SIZE INCH SYSTEM ISI DWG IIIINEER ISI-0269-C VENDOR ATWOOD C

MORRILL VENDOR DNE ND.

20788-H MATERIAL SPEC.

VALVE TYPE A-216 WCB CHECK COMMENTS HCV3-66 HCV3-67 FCV68-01 FCV68-77 FCV68-03 FCB68-79 FCV68-33 FCV68-35 28 28 22 RECIR RECIR RECIR ISI-0269-C POWELL ISI-0270-C DARLING ISI-0270-C DARLING ISI"0270-C DARLING 035879-2 94-12086 94"12086 94-12086 A3Sl CF8 GATE A351 CF8 GATE A351 CFB A-216 WCB GATE FCV1-14 FCV1-15 FCV1-26 FCV1-27 FCV1-37 FCV1-38 FCV1-51 FCV1-52 26 ISI-0222-C ATWOOD C

MORRILL 20851-H A216 WCB GLOBE RMWQSI46G

0 S

L REV 0008 2"SI-4 '.G Page 93 SECTION 8.3 ASME CLASS 1

E UIVALENT VALVE LIST (Continued)

GROUP NUHEER VALVE NURSER SIZE INCH SYSYEH ISI DWG llUHMR VENDOR VENDOR DWG NO.

MATERIAL SPEC.

VALVE TYPE COMMENTS PCV1-004 PCV1-005 PCV1-018 PCV1-019 PCVl-022 PCVl-023 PCVl-030 PCVl-031 PCV1-034 PCVl-041 PCVl-042 PCV1-179 PCV1-180 ISI-0312-B TARGET ROCK PL-7657-100 A216 WCB C A105 PILOT opeRATED RELIEF 10 12 15 HCV74-69 HCV74-55 FCV74 54 FCV74-68 FCV74-53

~

FCV74-67 HCV74-49 FCV74-47 85-577 24 20 20 ISI-0221-C POWELL ISI-0221-C ATWOOD C

MORRILL ISI-0221-C WALWORTH IS I-0272-C VELAN ISI-0221-C POWELL ISI-0221-C WALWORTH 035880-3 20800-H A-12334-M1E 036207-2 A-12332"MlC P-339231-13 A351 CF8M GATE

.A351 cF8M cHecK A351 CF8M GATe A351 CFBM GATE A216 WCB GATE A182 TP316 GATE No B-G-2 Bolting.

No B-G-2 Bolting.

Exempt from B-M-2 exam@.

Size (

4".

R:WWQSI46G

SECTION 8.3 ASME CLASS 1

E UIVALENT VALVE LIST (Continued) 2-SI-F 6.G Page 94 GROUP NIHEER 16 17 18 19 21 22 23 25 26 27 VALVE IIDHEER HCV75-27 HCV75-55 FCV75.-26 FCV75-54 FCV75-25 FCV75-53 69-500 FCV69-01 FCV69-02 69-579 69-580 FCV71"40 FCV73-02 FCV73-03 FCV73-45 FCV74-48 SIZE INCH 12 12 12 10 14 20 SYSYEH CS CS CS RWCU RWCU RWCU RWCU RCIC HPCI HPCI ISI DWG NUMBER ISI-0271-C ISI-0271-C ISI-0271-C ISI-0272-C ISI-0272-C ISI-0272-C ISI-0272-C ISI-0272-C ISI-0273-C ISI-0273-C ISI-0221-C VENDOR POWELL ROCKWELL WALWORTH ROCKWELL CRANE ROCKWELL WALWORTH VENDOR DNG ND.

MATERIAL SPEC.

VALVE TYPE 0360334-2 A351 CF8M GATE IVP-1198 A351 CF8M GATE P-33160-20 A182 F316 GATE P-33160-20 A182 F316 GATE P-35177-4 A105 GRll CHECK P"35177-3 A105 GR11 GATE PD-420688 A216 WCB PB-139989 A216 WCB CHECK PD-420687 A216 WCB CHECK A-12331-Mlc A351 CF8M GATE PD-420652 A351 CF8M CHECK COMMENTS NO B-G-2 bolting.

Exempt from B"M-2 exams.

Size 4".

Exempt from B-M-2 exams.

Size 4".

No B-G-2 bolting.

No B"G-2 bolting.

28 69-630 RWCU ISI-0272-C ANCHOR/

DARLING C23650 SA351 CF8M CHECK Exempt from B-M-2 exams.

Size NE 4" RWWQSI46G

REV 0008 2-SI-4.6.G Page 95 SECTION 8.4 REQVESTS FOR RELIEF RLRVh2S146G

2-S1-4.6.G Page 96 REQUEST FOR RELIEF ISI-2-1 WITHDRAWN RLRVA2SI46G

REV 0008 2-SI-4.6.G Page 97

~

REQUEST FOR RELIEF ISI-2-2 WITHDRAWN RWWQSI46G

2-SI-4. 6. G Page 98 REQUEST FOR RELIEF ISI-2-3

~Com agents:

Reactor Pressure Vessel Nozzle to Vessel Head Weld (N6 Nozzle)

Classification:

B-D Item Number:

B3.90 Ins ection Re irements:

ASME Section XI, Table IWB-2500-1, Examination Category B-D, Item Number B3.90, Volumetric Examination, Figure IWB-2500-7.

Basis for Relief:

The nozzle to head contour limits the accessible volume of examination performed from the O.D. to 60%.

Alternate Ins ection:

None.

RWVlh2SI46G

REQUEST FOR RELIEF ISI-2-4 2-SI-4.6 '

Page 99

~Com anents:

Class 1 Piping Welds (refer to attached list)

Classification:

B-F and B-J Item Number:

B5.130, 89.10, or B9.30 Ins ection Re uirements:

ASME Section XI, Table IWB-2500-1, Examination Category B-F and B-J piping welds greater than or, equal to NPS 4-inch Basis for Relief:

In some cases it is not possible to perform the volumetric ultrasonic examination from both sides of the weld due to configuration or permanent features such as piping supports or fire retardant insulation in the adjacent wall penetration.

Attached is a detailed description of the limitations for each weld listed and a summary of the scans performed.

Alternate Ins ection:

None.

RWVA2SI46G

REV 0008 REQUEST FOR RELIEF ISI-2-4 {Continued) 2-SI-4 '.G Page 100 WELD NUMBER DCS-2-03 CODE CAT.

B-J ITEM NUMBER B9.11 MAT'L.

SS SIZE NPS ISI DRAWING 12 ISI-0271-C CONFIGURATION VALVE TO BELLOWS CODE SCAN 37.4 No scan 3 or 4, limited scans 5

and 6

DCS-2-12 B-J B9. 11 SS 12 ISI-0271-C VALVE TO BELLOWS 37.4 No scan 3 or 4, limited scans 5

and 6

TCS-2-422 B-F B5 ~ 130 DM 12 ISI-0271-C PIPE TO VALVE 86.5 No scan 4,

limited scans 5

and 6

GMS-2-10 B-J B9. 11 CS 26 ISI-0222-C PIPE TO VALVE 86 No scan 3 and surface restriction DRHR-2-03 B-J TRWCU-2-02 B-J DRWC-2-01A B-J B9.11 B9. 11 B9. 11 SS SS SS ISI"0221-C ISI-0272-C ISI-0272-C VALVE TO FLUED HEAD VALVE TO VALVE VALVE TO WELDOLET 65 50 72 Limited due to surface contour No scans 3 or 4

Limited scans 3

and 4 due to configuration KR-2-01 B-J B9.31 SS ISI-0270"C PIPE TO WELDOLET 32 No scan 3 and limited scans 4,

5, and 6

RMWQSl46G

RHV0008 REQUEST FOR RELIEF ISI-2-4 (Continued),

2-SI-4.6.G Page 101 WELD NUMBER CODE CAT.

CONFIGURATION EXAMINATIONLIMITATIONDETAILS DCS-2-03 B-J Valve to Bellows 37.4 Basis for Relief No Scan 3 performed due to a stainless steel valve.

The combined effect of the valve surface taper and the anisotropic nature of the stainless material creates a scan limitation and prevents a scan from this side of the weld.

No scan 4 performed due to a bellows configuration.

Search unit contact is lost by the radius of curvature from the bellows side.

Scans 5 and 6 are limited due to the weld to fitting junction.

Loss of contact of the search unit impedes obtaining code coverage for scans 5 and 6.

Scans 5 and 6 were supplemented with a 45 degree refracted longitudinal wave search unit in order to maximize coverage.

The limitations are noted on t>>e ultrasonic examination data sheets.

Justification for Relief: TVA performed a surface and ultrasonic examination on accessible areas of the 12 inch circumferential valve to flued head weld, DCS-2>>03.

The design configuration of the subject weld limits ultrasonic examination preventing 100% code examination coverage.

==

Conclusion:==

Based on the above justification, it is concluded that the code requirements are impractical. TvA's supplemental examinations provide an acceptable level of quality and safety.

R:PL%QSI46G

RBV0008 2-SI-4 '.G Page 102 REQUEST FOR RELIEF ISI-2-4 {Continued)

WELD NUMBER CODE CAT.

CONFIGURATION SCAN 8

EXAMINATIONLIMITATIONDETAILS DCS-2-12 B-J Valve to Bellows 37.4 Basis for Relief No Scan 3 performed due to a stainless steel valve.

The combined effect of the valve surface taper and the anisotropic nature of the material creates a

scan limitation and prevents a scan from this side of the weld.

No scan 4 performed due to a bellows configuration.

Search unit contact is lost by the radius of curvature from the bellows side.

Scans 5

and 6 are limited due to the weld to fitting junction. Loss of contact of the search unit impedes obtaining code coverage for scans 5 and 6.

Scans 5 and 6 were supplemented with a 45 degree refracted longitudinal wave search unit in order to maximize coverage and improve attenuation loss by shear wave search units on weld metal.

Justification for Relief: TVA performed a surface and ultrasonic examination on accessible areas of the 12 inch circumferential valve to flued head weld, DCS-2-12.

The design configuration of the subject weld limits ultrasonic examination preventing 100$ code examination coverage.

==

Conclusion:==

Based on the above justification, it is concluded that the code requirements are impractical. TVA's supplemental examinations provide an acceptable level of quality and safety.

R:WWQSI466

RBY0008 2-SI"4.6.G Page 103 REQUEST FOR RELIEF ISI-2-4 (Continued)

WELD NUMBER CODE CAT.

CONFIGURATION EXAMINATIONLIMITATIONDETAILS TCS-2"422 B-J Pipe to Valve 86.5%

Basis for Relief No Scan 4 performed due to a stainless steel valve.

The combined effect of the valve surface taper and the anisotropic nature of the stainless material creates a scan limitation and prevents a scan from this side of the weld. Scans 5 and 6 are limited due to the weld to fitting junction. Loss of contact of the search unit impedes obtaining code coverage for scans 5 and 6. Scans 5 and 6 were supplemented with a 45 degree refracted longitudinal wave search unit in order to maximize coverage and improve attenuation loss by shear wave search units on weld metal.

Justification for Relief:

TVA performed a surface and ultrasonic examination on accessible areas of the 12 inch circumferential pipe to valve weld, TCS-2-422.

A high percentage of code coverage was obtained (86.5%).

The desigi configuration of the subject weld limits ultrasonic examination preventing 100% code examination coverage.

==

Conclusion:==

Based on the above justification, it is concluded that the code requirements are impractical. TVA's supplemental examinations provide an acceptable level of quality and safety.

R:WWQSI466

REV 0008 2-SI-4.6.G Page 104 REQUEST FOR RELIEF ISI-2-4 (Continued)

WELD NUMBER GMS-2-10 CODE CAT.

B-J CONFIGURATION Valve to Pipe 86 EXAMINATIONI IMITATION DETAILS Basis for Relief No scan 3 performed due to a valve.

The combined effect of the valve surface taper and the anisotropic nature of the material creates a limitation and prevents a scan from this side of the weld.

Scan 4 was limited due to fire retardant insulation inside the penetration.

Scan 4

was limited to a distance of lo9 inches from centerline for the 45 degree shear and a distance of,1.5 inches for the 60 degree shear.

Scans 5 and 6 are limited due to the weld to fitting junction. Loss of contact of the search unit impedes obtaining code coverage for scans 5

and 6.

Justification for Relief: TVA performed a surface and an ultrason c ex nat on on accessible areas of the 26 inch circumferential valve to pipe weld, GMS-2-10.

A h~chh ercenta e of code covera e was obtained 86%

. The design conf gurat on of the sub ect we d ts ultrasonic examination preventing 100% code examination coverage.

This limitation is due to permanent asbestos-type insulation installed inside the penetration up to the subject weld.

Removal requires:

l. A Design Change.Notice to revise drawings depicting removed insulation from the mechanical drywell penetration assemblies, 2.

a calculation to evaluate the impact of the removed insulation, 3.

a design and manufacturer of special metal reflective insulation sections to replace removed insulation, 4.

a work area ventilated tent to contain asbestos insulation,

5. insulation workers having to con J

with the requirements of working in both a contaminated area (C-Zone) and an asbestos hazard area.

==

Conclusion:==

Based on the above justification and hardship, a concluded that the coda tequttenento ate tnptacttcal.

TVA's supplemental examinations and high percentage of coverage provides an acceptable level of quality and safety.

. RMWQSI46G

REV 0008 2-SI-4.6.6 Page 105 REQUEST FOR RELIEF ISI-2-4 (Continued)

MELD NUMBER CODE CAT.

CONFIGURATION EXAMINATIONLIMITATIONDETAILS DRMR-2-03 B-J Valve to Penetration 65 Basis for Relief:

Scan 3 is limited due to a stainless steel valve.

The combined effect. of the valve surface taper and the anisotropic nature of the stainless material creates a

scan limitation however a best effort scan was perfon from this side of the weld in order to maximize coverage.

A 60 degree search unit was used to increase effective coverage.

Scan 4 limited due to a fluted head penetration.

Search unit scan area is limited by the penetration configuration.

A 60 degree search unit was used to increase effective coverage.

Scans 5 and 6 are limited due to the weld to fitting )unction.

Loss of contact of the search unit impedes obtained code coverage for scans 5 and 6. Scans 5 and 6 were supplemented with a

45 degree refracted longitudinal wave search unit in order to maximize coverage and improve attenuation loss by shear wave search units on weld metal.

Justification for Relief: TVA performed an ultrasonic examination on accessible areas of the 24 inch circumferential valve to flued head weld, DRHR-2-03.

'esign configuration of the subject weld limits ultrasonic examination preventing 100% code examination coverage.

==

Conclusion:==

Based on the above )ustification, it is concluded that the code requirements are impractical.

TVA's supplemental examinations provide an acceptable level of quality and safety.

R.WWQSI46G

REV 0008 2-SI-4.6.G Page 106 REQUEST FOR RELIEF ISI-2-4 {Continued)

CODE CAT.

CONFIGURATION EXAMINATION LIMITATIONDETAILS TRWCU-2-02 B-J Valve to Valve 50 Basis for Relief:

NOTE: THIS WELD WAS REPLACED PRIOR TO STARTUP DURING THE UNIT 2, CYCLE 6 OUTAGE DUE TO THe 69-580 VALVE REPLACEMENT TVA REQUEST FOR RELIEF IN ORDER TO MAINTAIN CODE PERCENTAGE REQUIREMENTS FOR THE FIRST PERIOD.

Best effort scan 3 performed from stainless steel v'alve side.

The combined effect of the valve surface taper and the anisotropic nature of the stainless material creates a scan limitation and prevents a meaningful scan from this side of the weld. Loss of search unit contact due to fitting taper radius was a ma)or contributor in the limitation noted.

Best effort scan 4 performed from stainless steel valve side.

Scans 5 and 6 were supplemented with a 45 degree refracted longitudinal wave search unit in order to maximize coverage.

Justification for Relief: TVA performed a surface and an ultrasonic examination on accessible areas of the 4 inch circumferential valve to valve weld, TRWCU-2-02.

==

Conclusion:==

The design configuration of the subject weld limits ultrasonic examination preventing 100% code examination coverage.

Based on the above )ustification, ii is concluded that the code requirements are impractical.

TVA's supplemental examinations provide an acceptable level of quality and safety.

R.'WWQSI466

l V'BV 0008 REQUEST FOR RELIEF ISI-2-4 (Continued) 2"SI-4.6.G Page 107 WELD NUMBER CODE CAT.

CONFIGURATION SCAN EXAMINATIONLIMITATIONDETAILS DRWC-2-01A B-J Valve to Branch Connec'tion 72 Basis for Relief:

Scans 3 and 4 are limited due to configuration, s

stainless steel valve is welded to a weldolet.

The combined effect of the branch connection and valve surface tapers and the anisotropic nature of the stainless material creates a scan limitation. However, a

best effort scan with a 46 degree refracted longitudinal wave transducer was performed on the weld crown in both axial directions in order to maximize coverage.

Justification for Relief: TVA performed an ultrasonic examination on accessible areas of the 6 inch circumferential valve to branch connection weld, DRWc-2-01A In addition, a post-weld crown reduction surface examinatioi was performed with no recordable indications detected.

The design configuration of the subject weld limits ultrasonic examination preventing 100% code examination coverage.

==

Conclusion:==

The design configuration of the subject weld combined with the anisotropic nature of the materials involved limits ultrasonic examination providing a constraint to achieving code examination coverage.

Ultrasonic examination techniques for the detection of IGSC<

revealed no evidence of stress corrosion cracking.

Additional ultrasonic search units and angles were utilized to maximize coverage.

Based on the above justification, it is concluded that the code requirements are impractical.

TVA's supplemental examinations provide an acceptable level of quality and safety.

RWWQSI466

REV 0008 2-SI-4. 6. G Page 108 REQUEST FOR RELIEF ISI-2-4 (Continued)

WELD NUMBER KR-2-01 CODE CAT.

B-J CONFIGURATION Pipe to Branch Connection 32 EXAMINATIONLIMITATIONDETAILS Basis for Relief:

No scan 3 and a limited scan 4 was performed due to configuration.

Scans 5 and 6 were performed;

however, code credit scan percentage was conservatively estimated (due to surface condition) and code credit was not taken.

The combined effect of the OD contour, component configuration, and component thickness, resulted in the scan limitations noted.

30 and 45 degree shear waves and a

45 degree refracted longitudinal scan were utilized for scan 4 (axial).

Justification for Relief: TVA performed an ultrasonic ex nat on on access ble areas of the 4-inch weldolet to 28-inch recirculation pipe weld, KR-2-01. The design configuration of the subject weld limits ultrasonic examination preventing 100% code examination coverage.

Scan 4 was supplemented with both a 30 degree shear wave and a

45 degree refracted longitudinal wave examination in order to maximize coverage.

In addition, a surface examination was performed with no unacceptable indications detected.

==

Conclusion:==

The design configuration of the subject weld ta <<ittaeonic examination pteoenting ltgt code examination coverage.

Ultrasonic examination techniques for the detection of IGSCC were applied with no crack-like indications noted.

Supplemental transducers and angles were utilized to maximize scan effectiveness and coverage.

Based on the above justification, it is concluded that the cong requirements are impractical.

TVA's supplemental examinations provide an acceptable level of quality and safety RMVA2SI46G 1

REV 0008 2-S1-4.6.G Page 109 Re uest for Relief ISI-2-5 (Vnit 2)

Camaonents:

Classification:

Longitudinal Welds in Class 1 and 2 Piping.

Class 1 and 2.

Code Cate pries>

B-J, C-F-1, and C-F-2.

Item Numbers:

B9 12'9

~22'S 12~

CS ~ 22 CS

~42'S

~ 52~

CS

~ 62 and C5.82.

Ins ection Re izements:

ASME Section XI, 1986 Edition, Table IWB-2500-1 requires a volumetric and/or surface examination be performed of at least one pipe diameter length but no more than 12 inches of each longitudinal weld that intersects a circumferential weld required to be examined under Code Category B-J.

ASME Section XI, 1986 Edition, Table IWC-2500-1 requizes a volumetric and/oz surface examination to be performed of at least 2.5t, where "t" is the thickness of each longitudinal weld that intersects a circumferential weld required to be examined under Code Categories C-F-1 and C-F-2.

Basis for Relief:

Longitudinal piping welds are fabricated during the manufacturing process under controlled shop conditions, which produce higher quality welds and more uniform residual stress patterns.

Longitudinal piping welds undergo heat treatment in the manufacturing facility, which enhances the material properties of the weld and reduces the residual stress created by welding.

Results of previous weld inspections throughout, the industry indicate that longitudinal welds have not been a safety concern, and there has been no evidence of longitudinal weld defects compromising safety at nuclear power plants.

Longitudinal welds have not been shown to be susceptible to any particular degradation mechanism.

The only areas of a longitudinal weld that may be suspect are the ends of the weld ad)acent to the field fabricated circumferential weld.

R:WVh2SI46G

REV 0008 2-SI" 4

~ 6. G Page 110 Basis for Relief (cont.):

Longitudinal welds are extremely difficult to locate even when the piping is identified as welded pipe. Typically, the existence and location of longitudinal welds must be determined by acid

etching, eddy current examination, or a combination of the two methods.

This results in an increase in personnel radiological exposure and generation of zadwaste above that incurred as a

result of performing the required examinations of the longitudinal welds.

The radiological exposure and cost associated with the inspection of longitudinal welds are dependent on the time it would take to remove and reinstall insulation and interferences, prepare the weld foz examination, and perform the examination.

Based on the above, the inspection of longitudinal welds as currently required by ASME,Section XI is not technically warranted.

The ASME Code Committee has recognized this fact and has published Code Case N-S24, "Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping Section XI, Division 1".

Alternate Ins ection:

As an alternative to the existing ASME,Section XI requirements, Browns Ferry Nuclear Plant will adopt the provisions of ASME Code Case N-524 for the examination of Class 1 and 2 longitudinal piping welds.

RWWQS146G

REV 0008 2-SI-4.6.G Page 111

~tom onents:

Reactor Pressure Vessel (RPV) Nozzle to Vessel Welds (refer to listing below for weld number identification)

Code Class:

Examination Cate or B-D Item Number:

B3. 90 and B3. 100 Code Re uizement:

B3.90 - Volumetric examination of the weld and ad)acent base material as specified in Figure IWB-2500-7 (Table IWB-2500-1, examination category B-D).

B3.100 Volumetric examination of the nozzle inner radius as specified in Figure IWB-2500-7 (Table IWB-2500-1, examination category B-D).

Code Re irement From Which Relief is

~Re ested:

Relief is requested from'the ASME Section XI requirement of performing volumetric examination of essentially 100t of the weld and base material volume specified in Figure IWB-2500-7 for the following RPV nazzle to vessel welds:

N1A, N2B, N2F, N2J, N3D, N4A,

N4F, N5A, and N8A. Relief is also requested fram the ASME Section XI requirement of performing volumetric examination of essentially 100% of the inner radius volume specified in Figure IWB-2500-7 for the RPV nozzle N8A.

Basis for Relief:

The RPV nozzle to vessel welds scheduled for examination during Unit 2, cycle 7 were examined utilizing the General Electric (GE)

GERIS 2000 automated scanning device from the vessel OD.

Each weld requires nine scans to achieve 100% coverage;

however, RPV nozxle design allows only seven scans and in some cases those aze limited. The limitations aze inherent to the barrel-type nozzle weld design and is compounded by the close proximity of the biological shield wall, approximately 11-inches away from the

RPV, and non-removable mirror insulatian.

Scanning fram the nozzle or bore side praduces sound beams oriented nearly parallel with the long axis of a postulated planar flaw and is therefare ineffective.

Use of additional angles or scanning from the nozzle taper or bore side does not result in an effective increase in coverage.

Coverage was maximized by supplementing with additional scans from the O.D. blend radius, where practical.

Access ta the vessel to nozzle welds is by a series of doorways in the concrete biological shield wall which swing open. Insulation in these doorways is designed for removal around the nozzle circumference.

RMWQSI46G

REV 0008 2-SI-4.6.G Page 112 Basis for Relief (cont.): Expezience from the performance of volumetric examinations conducted from the inside of the RPV on Unit 3, which is of similar design, has indicated that the vessel to nozzle weld access will not be greatly enhanced by the current state-of-the-azt techniques and that a relief request would still be necessary.

The coverage achieved for the vessel to nozzle welds examined during the Unit 2 cycle 7 outage is listed on the attached Table.

Coverage calculations were conservatively determined utilizing bi-directional coverage of the base material.

(Refer to Notes 1-2.)

Alternate Examinations:

Justification foz the Grantin of Relief:

NOTES:

Accessible portions of the RPV vessel to nozzle welds were ultrasonically examined from the vessel exterior utilizing the GERIS 2000 automated device.

Manual examination techniques from the O.D. blend radius were utilized to supplement the automated examination in order to maximize coverage where practical.

Since the accessible surfaces on the vessel side of the RPV vessel to nozzle welds were

scanned, there are no available alternative examinations.

TVA utilized a combination of state-of-the-azt automated ultrasonic examination performed by GE utilizing the GERIS 2000 device in conjunction with additional ultrasonic techniques where practical to maximize the coverage of the RPV nozzle to vessel welds.

The primary causal factor for the limitations encauntezed during performance of the ultrasonic examinations was related to the component design.

Based an a construction permit date of May 10, 1967 for BFN Unit 2 and as required by 10 CFR 50.55a(g) (1) and 10 CFR 50.55a(g) (4),

BFN must meet the requirements of ASME Section XI, except design and access provisions, ta the extent practical within the limitatians of design,

geametry, and materials of construction of the components.

BFN Unit 2 was not designed to provide access for ASME Section XI examinations.

(2)

Examination volume coverage calculatians are based upon the follawing ultrasonic scan nomenclature:

a) 0 degree weld metal scant b) 45 degree Transverse (T)-scan fram the vessel sidep c) 45 degree T-scan from the nozzle sides d) 60 degree T-scan from the vessel sides e) 60 degrees T-scan from the nozzle sides f) 45 degree Parallel (P) -scan clockwise (CS) directiong g) 45 degzee P-scan counter-clockwise (CCW) directiang h) 60 degree P-scan CW direction; i) 60 degree P-scan CCW direction.

The 45 and 60 degree T-scans (cue scans in Note 1) were typically not practical from the nozzle side for the nozzles listed in this relief request.

Partions of the remaining seven scans were limited due to the inherent design geometry, bialogical shield wall proximity, and/or nan-removable mirror insulation.

R'WVh2SI46G

RBV0008 2-SI-4.6aG Page 113 REQUEST FOR RELIEF ISI-2-6 (Continued)

WELD NUMBER N1A <Recirc. outlet) 28" CHM-1094"A NPB

~ZSZ Dzavin 60%

Raaakka 0 degree L-wave, 45 and 60 degree T-scans were restricted due to biological shield and thermo-couple.

45 and 60 degree T-scans from the OD blend radius were restricted due to the biological shield.

45 and 60 degree P-scans were restricted due to the biological shield.

No examinations were practical from nozzle side due to configuration.

N2B (Recirc. inlet) 12" CHM-1094-A N2F (Recirc. inlet) 12" CHM-1094-A 52'L 55%

Manual 0 degree L-wave and 60 degree T-scans, and automated 0 degree L-wave, 45 and 60 degree T-scans were restricted due to insulation.

No examinations were practical from nozzle side due to configuration.

0 degree L-wave and 60 degree T-scans were restricted due to insulation.

No examinations were practical from the nozzle side due to configuration.

N2J (Recirc. inlet),

12" CHM-1094-A 55%

0 degree L-wave and 60 degree T-scans were restricted due to insulation.

No examinations were practical from the nozzle side due to configuration.

N3D lMain Stm.)

26" CHM-1094-A 57%

0 degree L-wave, 45 and 60 degree scans were restricted and no examinations were practical from the nozzle side due to configuration.

N4A (Feedwater) 12" CHM-1094-A 59%

Automated 0 degree L-wave, 45 and 60 degree T-scans, 45 and 60 degree scans from the OD blend radius and manual 60 degree T-scans were restricted due to the adjacent N11A nozzle and insulation support ring.

No examinations were practical from the nozzle side due to configuration.

R.'PLWQSI46G

REV 0008 REQUEST FOR RELIEF ISI-2-6 (Continued) 2-SI-4 '.G Page 114 WELD NUMBER N4F (Feedwater)

DIN

~INZ Dracula 12" CHM-1094-A Remarks 0 degree L-wave, 45 and 60 degree T-and P-scans, 45 and 60 degree scans from the OD blend radius and manual 60 degree T-scans were restricted due to the adjacent insulation and insulation support ring. No examinations were practical from the nozzle side due to configuration.

NSA (Core spray)

]0 II CHM-1094-A 53%

0 degiee L-wave, 45 and 60 degree T-scans and OD blend radius scans were restricted due to insulation support ring.

45 and 60 degree P-scans restricted due to insulation support ring.

No examinations were practical from nozzle side due to configuration.

NBA (Instr. nozzle) 4" CHM-1094-A 68%

0 degree L-wave, 45 and 60 degiee scans were restricted and no examination was practical from the nozzle side due to configuration of the nozzle to vessel weld.

OD blend radius scans were not practical due to configuration.

N8A-IR 4"

CHM-1094-A 73'0

-60 and 70 degree scans and supplemental 80 degree scans were restricted.

No examinations were practical from the nozzle side due to configuration of the nozzle to vessel weld.

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REV 0008 2-SZ-4.6eG Page 115 Re uest for Relief ISZ-2-7 comeonenoe:

Class 1 Integral Welded Attachments

{refer to attached list)

Classification:

Code Cate ories:

B-K-1 Item Numbers:

B10.10 Code Re izement:

ASME Section XI, 1986 Edition (no addenda),

Table ZWB-2500-1, Examination Category B-K-1 integrally welded attachments greater than or equal to 5/8-inch thickness, Figure ZWB-2500-15.

Code Re uizement From Which Relief is Re ested: Relief is requested from the ASME Section XZ, Table IWB-2500-1, requirements to perform a volumetric or surface examination, as applicable, of essentially 100% of the examination volume/area.

Basis for Relief:

TVA is requesting relief from ASME Section XZ, 1986 Edition (no addenda) requirements related to the 100% examination of the requized weld and base material volume required by Figure ZWB-2500-15 foz Examination Category B-K-1 integrally welded supports.

The supports are identified on the attached list, which will be updated as required.

Examination of the accessible areas of the integral attachment welds without removal of support members would result in estimated savings of approximately

$ 110,000 for personnel and materials, and approximately 150 man-zems of exposure, which equates to $ 1,500,000 during the remaining inservice inspection intervals for a total Unit 2 savings of $1.6 million dollars.

ASME Section XI, 1986 Edition, Table IWB-2500-lg Examination Category B10.10, requires examination of essentially 100% of the weld and base material for integrally welded attachments.

In some cases this examination would require the removal of support members to achieve the coverage required by the 1986 Edition of ASME Section XZ.

Estimated duration for activities associated with the temporary removal of supports for the examination of integrally welded supports follow:

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REV 0008 2-SI-4.6.G Page 116 A~ctE vXt Engineering evaluation of temporary support Duration

{man-hzs) 20 Craft time for support member removal, installation of temporary support, and support reinstallation 100 Quality Contzol verification of activity An average man hour cost of $35/hour was utilized for the estimate along with approximately 25 supports requiring tempozary removal for the current inspection interval.

An average drywell exposure rate of 50 mrem/hr was utilized for the man-rem exposure estimate.

These values result in estimated savings of approximately

$ 110,000 for personnel and materials.

A cost of $ 10,000 per man-rem for the 150 man-rems of exposure estimated during the remaining inservice inspection intervals for Unit 2 would result in a savings of $ 1,500.000.

The Code of record requires examination of 100% of the Class 1 integrally welded attachments sub)ect to examination which precludes selection of alternate integrally welded attachments without interference to meet code requirements.

The 25 supports estimated as requiring disassembly to conduct the examination of the integrally welded attachments represent approximately 458 of the total number of integrally welded Class 1 supports in this code category sub)ect to examination.

Alternate Ins ection:

Perform the required examination method from Table IWB-2500-1, Examination Category B-K-1, on the accessible examination volume/area of the support integral attachment without removal of support members.

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REV 0008 2-SI-4.6.G Page 117 Justifica>'on for the Grantin of Relief:

The limitations encountered duzing performance of the surface examination were caused by component configuration.

Based on a construction permit date of May 10, 1967 for BFN Unit 2 and as required by 10 CFR 50.55a(g) (1) and 10 CFR 50.55a(g)(4),

BFN must meet the requizements of ASME Section XI, except design and access provisions, to the extent practical within the limitations of design,

geometry, and materials of construction of the components.

BFN Unit 2 was not design to provide access for ASME Section XI examinations.

The surface examination of the subject integral attachment from one side provides an effective assessment of the integral attachment's structural integrity.

The examination of the accessible areas without removal of support members was approved for a future code revision by the ASME Section XI committee during their March 1995 meeting (Subcommittee activity number IS195-08).

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REV 0008 REQUEST FOR RELIEF ISI-2-7 (Continued) 2-SI"4.6.G Page 118 CODE SUPPORT NUMBER CAT.

2-47B415S0009 B-K-1 2-47B415H0002 B-K-1 2-47B415H0004 B"K-1 ITEM NUMBER B10.10 B10 ~ 10 B10.10 IWA THK.

.75" 1.625" 1.625" ISI DRAWING ISI-0277-C ISI-0277-C ISI-0277-C 63%

88%

88%

REMARKS The integrally welded attachment is box shaped and welded on both sides.

Access is limited to the exterior weld and portions of the weld on the opposite side that are not on the interior of the box shape.

The integrally welded attachment consists of 4 lugs tl-5/8" wide by 2" long) which are welded on three sides with a pipe clamp on the un-welded end.

The pipe clamp is on a vertical section of a 12" Feedwater line and the examination was limited by the pipe clamp.

The integrally welded attachment consists of 4 lugs (1-5/8" wide by 2" long) wHich are welded on three sides with a pipe clamp on the un-welded end.

The pipe clamp is on a vertical section of a 12" Feedwater line and the examination was limited by the pipe clamp.

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REV 0008 2-SI-4.6.G Page 119 REQUEST FOR RELIEF ISI-2-7 (Continued)

CODE SUPPORT NUMBER CAT 2-47B415H0006 B"K"1 ITEM NUMBER B10. 10 IWA THK.

1.625" ISI DRAWING EXAM ISI-0277-C 88%

The integrally welded attachment consists of 4 lugs (1-5/8" wide by 2" long) which are welded on three sides with a pipe clamp on the un-welded end.

The pipe clamp is on a vertical section of a 12" Fecdwatcr linc and the examination was limited by the pipe clamp.

2-47B415H0008 B-K-1 2-47B415H00010 B-K-1 B10.10 B10.10 5 It 1.56" ISI-0277-C ISI-0277-C 88%

88%

The integrally welded attachment consists of 4 lugs (l-l/2" wide by 2" long) which are welded on three sides with a pipe clamp on the un-welded end.

The pipe clamp is on a vertical section of a 12" Feedwater line and the examination was limited by the pipe clamp.

The integrally welded attachment consists of 4 lugs (1-9/16" wide by 2" long) which are welded along both vertical sides with a pipe clamp on onc of the un-welded end.

The pipe clamp is on a vertical section of a 12" Feedwater line and the examination was limited by the pipe clamp.

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REV 0008 REQUEsT FOR RELIEF ISI-2-7 {Continued)

E-SI-4.6.G Page 120 CODE SUPPORT NUMBER CAT.

2-47B415H00012 B-K-1 ITEM NUMBER B10. 10 IWA THK.

1.625" ISI DRAWING ISI-0277-C 88%

The integrally welded attachment consists of 4 lugs (1-5/8" wide by 2" long) which are welded on three sides with a pipe clamp on the un-welded side.

The pipe clamp is on a vertical section of a 12" Feedwater line and the examination was limited by the pipe clamp.

2-47B415800023 B-K-1 2-47B415S00025 B"K"1 B10.10 B10.10 0 It 0 It ISI-0277-C ISI-0277-C 21%

21%

The integrally welded attachment consists of 4 lugs inside a

circular frame with shims adjacent to the lugs.

The examination is limited by the structural frame and shims.

The integrally welded attachment consists of 4 lugs inside a

circular frame which shims adjacent to the lugs.

The examination is limited by the structural frame and shims.

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