ML18037A768

Rev 3 to Surveillance Instruction 1/3-SI-4.6.G, ISI Program Units 1 & 3.

ML18037A768
Person / Time
Site:	Browns Ferry
Issue date:	10/21/1993
From:	Froscello F TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18037A765	List: ML18037A764 ML18037A766 ML18037A768
References
1-3-SI-4.6.G, NUDOCS 9403070218
Download: ML18037A768 (196)

Text

TENNESSEE VALLEY AUTHORITY BROMNS FERRY NUCLEAR PLANT SURVEILLANCE INSTRUCTION I/3-SI-4,6,G INSERVICE INSPECTION PROGM UNITS I AND 3 REVISION 3 PREPARED BY: F. M. FROSCELLO PHONE: 3524 RESPONSIBLE ORGANIZATION: NUCLEAR ENGINEERING APPROVED BY: M. BAJESTANI DATE: 10/21/93 EFFECTIVE DATE: 11/02/93 LEVEL OF USE', CONTINUOUS USE VALIDATION DATE: NOT REQUIRED QUALITY-RELATED 9403070218 940222 PDR ADOt.K 05000259 PDR

t t

(2043)

REVISION LOG Procedure Number: 1/3-SI-4.6.G Revision Number. '3 Pages Affected: 1, 4, 6-13, 37-43, 45-47, 50, 51, 79-91, 107-109, 111, 112, 144 Pagination Pages: 2, 3, 5, 14-36, 44, 48, 49, 52-78,92-106, 110, 113-143, 145-154 Description of Change:

21.0 references Table of Contents Appendix D & E (deleted).

Organizational and responsibility changes.

Added new requirements.

Renumber of paragraph and subparagraphs.

Deleted NOI (Notice of Indication).

Added new note to deal with existing NOI's.

Added paragraph sentence in paragraph 20.18 TVA to table ASNE XI Code Audit for RPV shell weld exams Unit 1 & 3 Added Wells to Table Appendix a Table D-1A & D-1B, D-3A, D-3B and revised tables.

Deleted Appendix D & E & f data sheet 3.

TVA to

t 1/3-SI-4.6.G Page l.

TABLE OF CONTENTS 1.0 STATEMENT OF APPLICABILITY 2.0 PURPOSE 3.0 INSPECTION INTERVALS AND INSPECTION CYCLES 4.0 CODES OF RECORD AND CODE CASES 5.0 METHOD OF IMPLEMENTATION AND RESPONSIBILITIES 6.0 ABBREVIATIONS AND DEFINITIONS 7.0 COMPONENTS SUBJECT TO EXAMINATION TVA CLASS 1 8.0 COMPONENTS SUBJECT TO EXAMINATION TVA CLASS 2 9.0 COMPONENTS SUBJECT TO EXAMINATION TVA CLASS 3 10.0 AUTHORIZED INSPECTOR 11.0 EXAMINATION METHODS t 12.0 13.0 14.0 15.0 16.0 QUALIFICATIONS OF NDE PERSONNEL ACCEPTANCE CRITERIA REPAIRS AND REPLACEMENTS PUMP AND VALVE TESTING RECORDS AND REPORTS 17.0 INSPECTION REPORTS 18.0 CALIBRATION BLOCKS 19.0 REQUEST FOR RELIEF 20.0 AUGMENTED EXAMINATIONS

21.0 REFERENCES

APPENDIX A Examination Schedule APPENDIX B List of ASME Section XI Boundary Drawings and ISI Drawings APPENDIX C Class 1 Valve Data

'PPENDIX D - Notification of Indication (deleted)

APPENDIX E Component Support Information (deleted)

APPENDIX F Data Sheets APPENDIX G Requests for Relief 1084(207)

1/3-SI-4.6.G 0" Page 2 STATEMENT OF APPLICABILITY This program outlines details for planning and performing the first interval inservice inspection (ISI) nondestructive examinations (NDEs) for Units 1 and 3 of Browns Ferry Nuclear Plant (BFN) Code Class 1, 2 and 3 equivalent components. The program is organized to fulfill ISI requirements of SSP-6.10, ASME Section XI Inservice Inspection Program; the 1974 Edition, Summer 1975 Addenda of Section XI of the ASME Boiler and Pressure Vessel Code; and applicable portions of the BFN Techn'ical Specification Surveillance Requirement 4.6.G. In accordance with 10 CFR Part 50, 50.55a(g), this program meets the ISI requirements to the extent practical.

Specifics concerning performance of NDE are not a part of this program but are included in NDE procedure (}MP 110.5.

ASME Section XI Boundary Drawings and ISI Drawings listed in Appendix B are issued and controlled through BFN Document Control and Records Management (DCRM) and are prepared/revised by M/N Engineering.

2.0 PURPOSE The ISI Program is employed to obtain data which can be used to determine if a component flaw is individual or of a generic nature, which would signal for examination of like components in the system.

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

The examinations required by this program shall establish acceptance for continued use of components during operation.

The ISI Program reflects the built-in limitations caused by original plant design, geometry, construction component materials, and the current technology or state-of-the-art nondestructive testing. The ISI Program shall also detail components to be examined, examination methods selected, and schedule charts for planning examinations.

3.0 INSPECTION INTERVALS AND INSPECTION CYCLES The inservice examinations required by ASME Section XI shall be performed during each inspection interval. 'The inspection intervals represent calendar years after the unit has been placed into commercial service. The first 10-year interval may be extended by as much as one year to permit inspections to be concurrent with plant outages (if the interval is extended, the following interval shall be decreased by an equivalent amount). If the unit is out of service continuously for one year or more, the inspection interval may be extended for an equivalent period.

The inspection interval shall be separated into three inspection cycles (40-month, 80-month, and 120-month). See Table 3.0-1 for important cycle and interval date information.

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t 1/3-SI-4.6.G Page 3' 3.0 INSPECTION INTERVALS AND INSPECTION CYCLES (continued)

Exce t for examinations that ma y be deferred to the e nd of the inspection interval, the required examinations shall be performed in accordance with the following schedule.

E Minimum Examinations Maximum Examinations Ins ection C cle Com leted Com leted 40-month 25 33-1/3 80-month 50 66-2/3 120-month 100 100 The examinations deferred to the end of the inspec'tion interval shall be completed by the end of the inspection interval.

ISI Program O-SI-4.6.G incorporated Units 1, 2, and 3 into a concurrent cycle (letter to the Nuclear Regulatory Commission (NRC) LOO 801231 705) beginning July 1, 1980. By extending the inspection interval one year (IWA-2400), the 80-month inspection cycle began on July 1, 1981.

TABLE 3.0-1 t

BROWN FERRY NUCLEAR PLANT P.Oe BOX 2000 DECATUR, AL 35609 COMMERCIAL CONCURRENT 80-MONTH 120-MONTH END OF FIRST UNIT OPERATION CYCLE CYCLE START CYCLE START 10-YEAR INTERVAL 1 8-1-74 7-1-80 7-1-81 11-1-84 One year after startup from extended outage.

3 3-1-77 7-1-80 7-1-81 11-1-84 One year after

'tartup from extended outage.

140-month cycle was extended by one year (IWA-2400). The second 10-year interval shall only be nine years.

2The program submittal for the second 10-year interval shall be based on the code in effect at the time of startup of each unit after the extended outages of the 1984 to 1990's plus time period.

Effective May 24, 1992, the Unit 2 program was incorporated into 2-SI-4.6.G.

Units 1 and 3 were incorporated into this program (1/3-SI-4.6.G).

Name and Address of Owner: Tennessee Valley Authority

.Chattanooga, Tennessee 37401 1084(207)

t 1/3-SI-4.6.G Page 4 4.0 CODES OF RECORD AND CODE CASES 4.1 Current Code Re uirements and Code Cases This program was prepared to meet the'equirements of the 1974 Edition, Summer 1975 Addenda of Section XI of ASME Boiler and Pressure Vessel Code. Beginning on June 12, 1992, NDE methods, qualification of personnel, weld reference system, and standards for examination evaluation shall be in accordance with the 1986 Edition of ASME Section XI (TAC No. M82171, A02 920429 005).

This shall include all portions of IWA-2200, IWA-2300, IWA-2600, IWA-3000, IWB-3000, IWC-3000, IWD-3000, and IWF-3000, as well as all portions of Appendices III, IV, and VI of ASME Section XI.

Certification of NDE personnel shall be in accordance with the 1984 Edition of ASNT SNT-TC-1A as approved by the Nuclear Regulatory Commission's letter from S. C. Black to 0. D.

Kingsley, Jr., dated January 18, 1990 (TAC No. 72833). Class 2 pressure-retaining bolting which exceeds two inches in diameter shall be volumetrically examined in accordance with Table IWC-2500-1, Examination Category C-D of the 1977 Edition, Summer 1979 Addenda of ASME Section XI. Class 2 pressure-retaining bolting two inches or less in diameter shall not be examined (Request for Relief ISI-14). Preservice inspection of pipe welds shall be performed in accordance with the 1977 Edition, Summer 1978 Addenda of ASME Section XI. See Section 14.0.

Code Cases N-234, 235, 307-1, 308, 341, 356, 416, 435-1, 460, and 461 that were approved by Regulatory Guide 1.147 are being used at BFN for the ISI Program.

4.2 Histor of Codes of Record and Code Cases For Units 1 and 3, 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.

4.2.1 For Unit 1, the history of the ASME Section XI Code of Record and Code Cases used is as follows:

A. The first period of the first interval in effect from August 1, 1974 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 for 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.

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1/3-81-4.6.G Page 5'.

The second period (July 1, 1981 through November 1, 1984) and the third period (November '1, 1984 through date to be determined) 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 XI for these periods. This included examination per IWA-2232(b), IWA-2232(c),

and Appendix III (to the extent specified in Request for Relief ISI-15 contained in Appendix G) and evaluation per IWA-3000, IWB-3000, and IWC-3000 of, the 1977 Edition, Summer 1978 Addenda.

In accordance with TVA's letter to the NRC dated March 1, 1988 (L44 880301 801), the second inspection interval for each BFN unit shall commence one year after startup from the extended outages of 1984 to an indeterminate date for. Units 3 and 1 (May 24, 1992 for Unit 2).

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

4.2.2 For Unit 3, the history of the ASME Section XI Code of Record and Code Cases used is as follows:

A. The first period of the first interval (March 1, 1977 through July 1, 1981), the second period (July 1, 1981 through November 1, 1984) and the third period (November 1, 1984 through date to be determined) were to the 1974 Edition with Addenda through Summer 1975 of ASME Section XI. Ultrasonic examination and evaluation of piping welds were upgraded to the 1977 Edition Summer 1978 Addenda of ASME Section XI beginning July 1, 1991. This included examination per IWA-2232(b), IWA-2232(c),

and Appendix III and evaluation per IWA-3000, IWB-3000, and IWC-3000 of the 1977 Edition, Summer 1978 Addenda.

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

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1/3-SI-4.6.G Page 6 5.0

~ METHOD OF IMPLEMENTATION AND RESPONSIBILITIES 5.1

~ Cor orate En ineerin Materials & Ins ection M 5 I res onsibilities'.

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

B. Providing assessment and oversite of this program and ISI activities on site.

C. Review and comment all PSI/ISI Program Requests For Relief prior to issuance.

5.2 Mechanical/Nuclear M/N) En ineerin 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, Revision 3.

B. Preparing/Revising ASME Section XI Code Class Boundary Drawings to identify the ASME Section XI Class 1, 2, and 3 equivalent boundaries within each plant system. See Appendix B for drawing list.

C. Preparing/Revising ASME Section XI ISI Drawings that identify the Class 1, 2, and 3 equivalent components (including supports) that require inservice and/or preservice NDE to comply with ASME Section XI requirements. See Appendix B for drawing list.

D. Preparing/Revising this instruction (ISI Program) and submitting it to:

1. DCRM for approval and issue as a controlled document.

2. Site Licensing for subsequent submittal to the NRC.

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1/3-SI-4.6.G Page 7~

5.0 METHOD OF IMPLEMENTATION AND RESPONSIBILITIES (continued)

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 Drawings.

5. An examination schedule providing the total number of each code item number, the number of samples for 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 'RFRs.

9. Name and address of the owner.

10. Name and address of generating plant.

11. 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 identifiers, NDE procedure, calibration standard reference, ISI Drawing number, sheet number, etc.

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

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t 1/3-SI-4.6.G Page 8 5.0 METHOD OF IMPLEMENTATION AND RESPONSIBILITIES (continued)

F. Providing ISI and/or PSI ASME Section XI interpretations with assistance from Corporate Engineering, Materials & Inspection (M & I) as requested by various site organizations or as required in program development and implementation.

G. Providing a list of components scheduled examination during each refueling outage to M & I for scan plan development.

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

H. Approving revisions to scan plans affecting component selection or any provision of the listing of components identified in Section 5.2.G.

Providing any additional samples required due to examinations performed.

Preparing an RFR when required because of areas that are inaccessible or partially inaccessible for examination or because it is determined that conformance with Code I shall notify requirements is impractical. M & M/N Engineering if limited examinations indicate the need to initiate an RFR.

K. Ensuring that RFRs, including supporting information and any alternative examinations, are documented.

L. Submitting RFRs to the Site Licensing organization.

M. Providing/coordinating dispositions for inspection reports (IRs) in accordance with SSP-3.1. See Section 17.2.

N. Performing NDE per the requirements of this instruction.

0. Ensuring that ISI/PSI examinations are performed in accordance with TVA NDE procedures or in accordance with contractor procedures that have been authorized for use by M&I.

P. Administering Authorized Inspection Agency (AIA) contract and ensuring that services of AIA are used when performing Code required activities. TVA's interface with the Authorized Inspection (AI) for ISI, repairs, and replacements is defined in SSP-6.9 and SSP-6.10.

1084(207)

1/3-SI-4.6.G Page AND RESPONSIBILITIES (continued) 9'MPLEMENTATION Providing AIA representative with access to plant and documentation in accordance with IWA-2140 of ASME Section XI.

R. Notifying ANII prior to performing examinations.

S. Preparing IRs and documenting followup examinations, and assuring closure and proper filing.

Preparing examination reports and recording them (report number, date, examiner's initials, and comments/IR number) in the scan plan. When inservice examinations are implemented by instructions other than this program (i.e., MMIs), 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.

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

V. Preparing ISI Summary Reports, preparing augmented examination summary reports, obtaining ANII signature on NIS-1 form, coordinating summary report reviews with M & I and submitting ISI and augmented examination Summary Reports to Site Licensing.

W. Preparing and submitting Site Final Report to DCRM as a Quality Assurance (QA) record.

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

Y. Calculation of component support acceptance ranges, if required, in accordance with QMP-110.5, N-GP-7, and N-VT-1.

Z. Maintaining calibration blocks stored at the plant site.

AA. Initiating a pre-outage meeting on augmented examinations per Section 20.0.

1084(207)

t 1/3-SI-4.6.G Page 10 f

5.0 METHOD OF IMPLEMENTATION AND RESPONSIBILITIES (continued) 5.3 Site En ineerin res onsibilities:

A. Designing, fabricating, erecting, and constructing components to quality standards commensurate with the safety function to be performed. This includes designing for access in accordance with ASME Section XI, IWA-1400(b), and INA-1500.

B. Performing engineering evaluations in support of IR dispositions or other examinations indications.

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

D. Providing specific w'ritten details for any augmented requirements for which they are responsible per Section 20.0 and determining if a post examination meeting is required.

5.4 Site Licensin res onsibilities:

A. Filing this Surveillance Instruction (1/3-SI-4.6.G) and revisions with the NRC per IWA-1400(c). M/N Engineering should be included on distribution of correspondence.

B. Submitting RFRs and summary reports to the NRC. M/N Engineering should be included on distribution of all related correspondence.

5.5 M 6 I res onsibilities:

A. Preparing/Revising scan plans for each refueling outage of the inspection interval utilizing MELD. This includes providing additional information provided by NDE Level III personnel to complete the scan plan, such as NDE procedure references, calibration standard references, and UT scanning angles.

B. Providing NDE Level III approval of scan plan revisions that affect the additional information of Section 5.5.A and maintaining a scan plan revision history log.

C. Providing NDE Level III determination if an RFR is required because of areas that are 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.

0 1084(207)

~ '

1/3-SI-4.6.G

~"

Page 11 METHOD OF IMPLEMENTATION AND RESPONSIBILITIES (continued)

D. Approving contractor NDE procedures, contractor written practices for qualification and certification of NDE personnel and certifications of contractor's NDE personnel performing ISI/PSI.

E. Providing.NDE Level III evaluation of successive examinations.

F. Packaging radiographs for storage and providing them with reader sheets to DORM as a life of plant record.

G. Providing copies of QMP-110.5 NDE procedure revisions and evidence of personnel qualifications to DCRM as RIMS records for the service lifetime of the plant in accordance with IWA-1400(k).

H. Maintaining as-built calibration standard drawings.

5.6 Site Document Control and Records Mana ement DORM) res onsibilities'.

A. Issuing controlled copies of ASME Section XI Code Class Boundary Drawings and ISI Drawings to specified distribution lists.

B. Issuing this program as an SI and providing controlled copies to M & I, the ANI/ANII, M/N Engineering, and other organizations as requested.

C. Maintaining the Site Final Report as a QA life of plant document. Other records referenced in the final report (work plans, radiographs, etc.), NDE procedure revisions, and evidence of personnel qualifications shall be retained for the service lifetime of the plant.

5.7 The Authorized Nuclear Inservice Ins ector (ANII) res onsibilities:

A. Performing the duties of IWA-2120.

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

5.8 Pro'ect Mana ement Res onsibilities:

A. Providing specific written details for any augmented requirements for which they are responsible per Section 20.0 and determining if a post examination meeting is required.

5.9 Nuclear Assurance and Licensing is responsible for reviewing insepction plans and/or quality assurance programs submitted by contractors.

1084(207)

1/3-SI-4.6.G Page 12 5.10.1 S stem for Maintainin Status of Examinations A. Data Base M & I and M/N Engineering shall utilize a computerized data base, WELD/PRISM, for maintaining the status of completed examinations for ASME Section XI credit and for augmented credit. See Sections 5.5.A and 5.5.B.

B. Scan Plan The Scan Plan is the primary scheduling document that is developed by M 6 I from WELD/PRISM. It should contain as a minimum:

components to be examined, Code Examination Category, Code Item Number, methods of examination, NDE procedure reference, calibration standard reference, ISI drawing number and sheet number, and for UT, the scanning angles. See Sections 5.2.A, 5.2.G, 5.5.A, 5.5.B, and 5.5.C.

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

(3) When inservice examinations are performed as a result 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 -5.2.T.

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1/3-SI-4.6.G Page 13 5.10 Im lementation (Continued)

(4) During implementation phases, it may become

'necessary to revise the scan plan. Scan Plan revisions may be initiated by M/N Engineering, M & I, 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. M 6 I shall maintain a scan plan revision history log. Interim working copies may be handwritten to allow examinations to be performed 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 5.2.A or Section 5.5.B.

Approving individuals shall initial and date such changes.

C. Configuration Changes Mhen 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 are made during the service lifetime of the unit, the changes shall be marked on field corrected copies of the appropriate drawing listed in Appendix B 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 5.10.B.(4) to reflect any PSI examinations performed due to the variations in configuration. See Section 5.2.C.

1084(207)

t 1/3-SI-4.6eG Page 14 6.0 ABBREVIATIONS AND DEFINITIONS 6.1 AIA - Authorized Inspection Agency.

6.2 AI Authorized Inspector (may denote an ANI or ANII).

6.3 ANI Authorized Nuclear Inspector.

6.4 ANII Authorized Nuclear Inservice Inspector.

6.5 ~Com onents Denotes items in a nuclear plant such as pressure vessels, piping systems, pumps, valves, and component supports.

6.6 Examination Denotes the performance of all visual observation and nondestructive testing such as radiography, ultrasonic, eddy current, liquid penetrant, and magnetic particle methods.

6.7 ~Ins ection Denotes verifying the performance of examinations and tests by an Inspector representing an Authorized Inspection Agency.

6.8 Maintenance Those normal functions performed to maintain equipment and systems in an operable status. This work includes but is not limited to the following:

Disassembly and reassembly of mechanical joints except where a replacement has taken place.

Lapping or skim cutting on valve seating surfaces.

Use of injection sealants (e.g., furmanite) or molecular metal (e.g., belzona). Installation of fittings into the pressure boundary for use of injection sealants is a modification activity.

Buffing, polishing, honing, sandblasting, and other metal removal for purposes other than defect removal.

Surface preparation for NDE, including removal of weld spatter.

Maintenance activities are exempt from the requirements of this instruction.

6e9 Normal 0 eration Normal plant operation conditions include reactor startup, operation at power, hot standby, and reactor cooldown to cold shutdown conditions. Test conditions are excluded.

6.10 Pressure-Retainin Material Applies to items such as vessel heads, nozzles, pipes, tubes, fittings, valve bodies, bonnets, disks, pump castings, covers, and boltings which join pressure-retaining items.

1084(207)

t 1/3-SI-4.6eG Page 15 6.0 ABBREVIATIONS AND DEFINITIONS (continued) 6.11 ~Re air Those operations involving welding; heat treatment, or defect removal which are required to restore a component or piping system to a safe and satisfactory operating condition.

6.12 subassemblies or parts of a component or system. It also includes the addition of components (such as valves) and/or system changes (such as deletion of components and rerouting of piping).

7.0 COMPONENTS SUBJECT TO EXAMINATION TVA CLASS 1 The Class 1 components to be examined during the inspection interval are outlined in the following paragraphs. The entire length of each weld described shall be examined for the first inspection interval unless otherwise noted. When a portion of a weld length is to be examined during an inservice examination, the areas examined shall be documented (length examined, location, etc.) on the examination data sheet.

All Class 1 components are subject to volumetric, and/or surface examination except components (and their supports) that are three-inch nominal pipe size and smaller (IWB-1220(b)(1) and (b)(3) of ASME,Section XI).

Table A of Appendix A supplies additional information such as distribution of examinations during inspection cycles, reference drawing numbers, and ASME Section XI, Table IWB-2500, Examination Categories.

7.1 Reactor Vessel 7.1.1 Reactor Vessel Seam Welds s

Certain welds listed in this section are not accessible due to sacrificial shielding. No alternate inspection is proposed (see RFR ISI-2). Drawing CHM-1095-A, sheets 1-'5, show ty'pical cross sections of the various welds to be examined.

7.1.1.1 Lon itudinal and Circumferential Seam Welds in There are two circumferential and six longitudinal seam welds in this region. All seam welds in the core region are inaccessible for ISI.

The shell course is a cylindrical weldment fabricated of manganese-molybdenum steel (chemistry in RPV manual), and is clad internally with weld deposited austenitic stainless steel.

1084(207)

1/3-SI-4.6.G Page 16 7.0 COMPONENTS SUBJECT TO EXAMINATION TVA CLASS 1 (continued) 7.1.1.2 Lower Head Seam Welds k

There are ten longitudinal seam welds and two circumferential seam welds in this region. All the seam welds in the lower head/region are inaccessible for ISI due to vessel shielding.

The hemispherical lower head is fabricated of, formed and welded sections of manganese-molybdenum steel (chemistry in RPV manual), and is clad internally with weld deposited inconel.

7.1.1.3 Vessel Seam Welds Not in Core Re ion There are 9 longitudinal welds outside the core region (totaling 78 feet). In accordance with the SER, 10 percent of this 78 feet of weld in addition to 10 percent of an additional 49 feet to represent the longitudinal weld in 7.1.1.2 above shall be examined during the inspection interval. A total of 13.0 feet of longitudinal weld (3.2 feet, of three welds [V-5-A, V-S-B, and V-5-C], 2.0 feet of weld V-3-A, and 0.5 feet of 3 welds [V-4-A, V-4-B, and V-4-C])

shall be ultrasonically examined.

There are 3 circumferential welds in this region (totaling 207 feet). In accordance with the SER, 5 percent of this 207 feet of weld in addition to 5 percent of an additional 93 feet to represent the circumferential weld in 7.1.1.2 above shall be examined during the inspection interval. A total of 15.2 feet of circumferential weld (seams C-3-4 and C-4-5) shall be ultrasonically examined.

The shell course is a cylindrical forged weldment fabricated of manganese-molybdenum steel (chemistry in RPV manual), and is clad internally with weld deposited austenitic stainless steel.

1084(207)

1/3-SI-4.6.G Page 17 7.0 COMPONENTS SUBJECT TO EXAMINATION TVA CLASS 1 (continued) 7.1.1.4 Closure Head Seam Welds There are 6 meridional welds, totaling 48 feet; 10 percent of each weld (0.8 feet) is required to be examined during the inspection interval.

To simplify, the examination, 1 foot of each of the 6 welds (RCH-X-lV, -2V, -3V, -4V, -5V, and

-6V) shall be ultrasonically examined. There is 1 circumferential weld (RCH-X-1C), totaling 38 feet; 5 percent (2 feet) of this weld shall be ultrasonically examined during the inspection interval.

The hemispherical dome segment is fabricated of formed and welded sections of manganese-molybdenum steel (chemistry in RPV manual).

The closure head is not clad.

7.1.1.5 Vessel-to-Flan e Weld The vessel-to-flange weld (C-5-FLG) is 69 feet long and is accessible for ISI. The entire length of the weld shall be examined during the inspection interval. The ISI of this weld shall be performed by ultrasonic techniques.

The flange is fabricated of ASTM-508 manganese-molybdenum steel conforming to Code Case 1332-2 and is clad internally with weld deposited austenitic stainless steel.

7.1.1.6 Head-to-Flan e Weld The head-to-flange weld (RCH-X-2C) is 66 feet long and is accessible for ISI. The entire length of the weld shall be examined during the inspection interval.

The flange forging is ASTM A-508 CL.2 steel conforming to ASME Code Case 1332-2. It is not clad.

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1/3-SI-4.6.G Page 18 7.0 COMPONENTS SUBJECT TO EXAMINATION TVA CLASS 1 (continued) 7.1.2 Reactor Vessel Nozzles All nozzles greater than 3-inch nominal pipe size shall be examined during the first inspection interval. Areas to be examined are the nozzle-to-vessel weld, nozzle inside radii at all positions, and nozzle-to-safe end weld.

The nozzles are fabricated of materials listed in the table below.

Nozzle Material Safe-End Material Main Steam ASTM A-508 CL.2 SA-105, Gr. II Feedwater ASTM A-508 CL.2 SA-105, Gr. II Core Spray ASTM A-508 CL.2 SA-376, Type 316 CRD ASTM A-508 SA-336$ CL F8 Recirculation (Inlet and Outlet) ASTM A-508 SA-376, Type 316 Jet Pump Inst. ASTM-A-508 SA-336$ CL F8 Head Vent ASME A-508 CL.2 SA-105, Gr. II Wld.

Neck Flg.

Head Inst. ASME A-508 CL.2 SA-105, Gr. II Wld.

Neck Flg.

The safe-ends for the main steam and feedwater nozzles are not dissimilar metal safe-ends. The remaining nozzles have buttered ends with the, specified safe-ends attached.

Drawing CHM-1094-A, sheets 1-,7, (Appendix B) show the typical weld cross sections. Table A of Appendix A outlines the size of each nozzle and scheduled inspections.

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t 1/3-SI-4.6.G Page 19 7.0 COMPONENTS SUBJECT TO EXAMINATION TVA CLASS 1 (continued) 7.1.3 Reactor Vessel Studs Nuts Nashers'ushin s and,

~Flan a L~lamanta The examinations shall cover 100 pere'ent of the closure

'studs (92), nuts, washers, and flange ligaments between threaded stud holes during the inspection interval. The studs and ligaments shall be ultrasonically examined, the nuts shall be ultrasonically and magnetic particle examined, and the washers shall be visually examined.

Table A of Appendix A outlines the schedule of examinations.

In addition, the closure studs shall be ultrasonically and magnetic particle examined when removed fxom the vessel. The bushings shall be visually examined when the closure studs are removed. These examinations need be performed only once during the inspection interval.

The bolting may be examined in place under tension, when the connection is disassembled, or when the bolting is removed.

Removal of the closure head assembly is in accordance with MMI-l, and provides for the examinations listed.

The studs, nuts, and washers are fabricated of alloy steel ASTM A-540 Gr. B-23 or 24, conforming to ASME Code Case 1335-2, Paragraph 4, Class 3.

7.1.4 Reactor Vessel Pressure Retainin Boltin Two Inches and Smaller in Diameter There is no pressure retaining bolting two inches or smaller in diameter.

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t

.1/3-SI-4.6.G Page 20 7.0 COMPONENTS SUBJECT TO EXAMINATION TVA CLASS 1 (continued) 7.1.5 Control Rod Drives and Penetrations The CRD housing welds are exempted from vo'lumetric examination by meeting the makeup exclusion criteria of IWB-1220 (b) (1) of ASME Section XI (see RFR ISI-6).

All 40 peripheral CRD housing welds shall be visually examined during system pressure tests to meet the alternate inspection.

There are 55 flux monitor penetrations, 1 level control nozzle penetration, and 1 drain nozzle penetration in the lower head. There are 6 instrumentation nozzle

.penetrations in the vessel shell. At least 25 percent of each group of penetrations of comparable size and function shall be visually examined for signs of leakage during system pressure in accordance with IWA-5240, ASME Section XI.

System pressure tests and VT-2 examination of the penetrations are included in SSP-8.5.

7.1.6 Reactor Vessel Su ort Skirt Weld There are four feet of support skirt weld accessible for inservice examination. The weld is accessible in two-foot lengths, 180 degrees apart (30 and 210 degrees). The four feet of weld shall be ultrasonically examined during the inspection interval (see RFR ISI-3). Drawing CHM-1091-A shows a typical cross section of the weld.

Table A of Appendix A outlines the schedule and method of the examinations. The support skirt is fabricated of SA-302, Grade B hull steel.

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1/3-SI-4.6.G Page 21 7.0 COMPONENTS SUBJECT TO EXAMINATION TVA CLASS 1 (continued) 7.1.7 Reactor Vessel Claddin Six austenitic stainless steel clad patches (each 6 x 6

= 36 square inches) have been prepared in the cladding and marked for ease of identification. The visual examinations shall cover 100 percent of each of the patch areas during the inspection interval. The examination shall be accomplished using the underwater TV camera. This must be coordinated with the refueling program in order to eliminate any unnecessary delays.

Color photographs, video tapes, or other recording systems of the inspection areas may be used for comparison with earlier visual records.

The reactor vessel head is not clad.

Reactor Vessel 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 three-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, jet 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 for BFN vessel internal examinations during the ISI interval are stated in Section 20.17 of this program.

This examination may be performed at or near the end of the inspection interval.

The general surveillance of the reactor vessel internals is in accordance with MMI-182.

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1/3-SI-4.6.G Page 22 7.0 COMPONENTS SUBJECT TO EXAMINATION TVA CLASS 1 (continued) 7.2 Pi in Pressure Boundar The ultrasonic examinations for the inspection interval shall include 100 percent of the area of approximately 25 percent of the Class 1 circumferential weld joints, larger than 3 inches, 100 percent of the Class 1 dissimilar metal weld joints, larger than 3 inches, and 1 foot of the adjoining sections of longitudinal weld joints. Also approximately 25 percent of the branch connections larger than 6 inches in diameter shall be ultrasonically examined. .Surface examinations shall include approximately 25 percent of the branch connections 6 inches in diameter and smaller, but greater than 3 inches in diameter.

Several welds are inaccessible for ISI. These welds shall be given a "best effort" visual examination during system pressure tests (see RFR ISI-7).

Several welds cannot be examined in accordance with paragraph T-532 of Article 5, ASME Section V, but they are not totally inaccessible. These welds shall receive a "best effort" ultrasonic examin'ation and a surface examination of accessible areas of the weld. These welds shall be noted as requiring the additional surface examination on the ultrasonic examination data sheet (see RFR ISI-S).

Several longitudinal welds are partially inaccessible for examination. No alternate examination is proposed.

7.2.1 Recirculation Pi in The Class 1 recirculation piping welds are identified and located on drawings listed in Appendix B. The examinations for this inspection interval are scheduled in Table A of Appendix A. Augmented examinations are discussed in Section 20.0, Au mented Examinations.

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.1/3-SI-4.6.G Page 23 7.0 COMPONENTS SUBJECT TO EXAMINATION TVA CLASS 1 (continued) 7.2.2 Main Steam Pi in The Class 1 main steam piping welds are identified and located on drawings listed in Appendix B. The examinations for this inspection interval are scheduled in Table A of Appendix A. Inaccessible welds are discussed in RFR ISI-7 in Appendix G. The pipe whip protection welds are also scheduled in Table A and are listed individually in Table C of Appendix A.

7.2.3 Feedwater Pi in The Class 1 feedwater piping welds are identified and located on drawings listed in Appendix B. The examinations for this inspection interval are scheduled in Table A of Appendix A. Inaccessible welds are

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discussed in RFR ISI-7 in Appendix G. The pipe whip protection welds are also scheduled in Table A and are listed individually in Table C of Appendix A.

7.2.4 Core S ra Pi in The Class 1 core spray piping welds are identified and located on drawings listed in Appendix B. The examinations for this inspection interval are scheduled in Table A of Appendix A. Inaccessible welds are discussed in RFR ISI-7 in Appendix G. The pipe whip.

protection welds are also scheduled in Table A and are listed individually in Table C of Appendix A.

7.2.5 Residual Heat Removal (RHR) Pi in The Class 1 RHR piping welds are identified and located on drawings listed in Appendix B. The examinations for this inspection interval are scheduled in Table A of Appendix A. Inaccessible welds are discussed in RFR NISI-7 in Appendix G. The pipe whip protection welds are also scheduled in Table A and are listed individually in Table C of Appendix A. [NRC/C] As required by NRC IR 86-03 (Open Item 86-03-03), weld DSRHR-2-5A shall be inspected using RT and UT every 1/3 inspection interval

[NRC IR 86-03]. See augmented requirement Section 20.18.

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t 1/3-SI-4.6.G Page 25 7.0 COMPONENTS SUBJECT TO EXAMINATION TVA CLASS 1 (continued) 7.3 Pi in Pressure-Retainin Boltin There is no pressure-retaining bolting 2 inches or larger in diameter in any of the Class 1 piping systems within the scope of this program.

There are 18 pressure-retaining bolted connections with bolting smaller than 2 inches in diameter that shall be given a visual examination that shall cover 100 percent of the bolts, studs, and nuts during the inspection interval. The bolting may be examined either in place, when the connection is disassembled, or when the bolting is removed. See Table A of Appendix A for scheduled examinations.

E 7.4 Com onent Su orts 7.4.1 Inte rail Welded Su ort Attachments The Class 1 integral attachments are identified and located on the support location drawings identified in Appendix B. The surface examinations to be performed in lieu of volumetric examinations (see RFR ISI-9 in Appendix G) are scheduled in Table A of Appendix A.

7.4.2 Com onent Su orts The Class 1 supports are identified and located on the support location drawings identified in Appendix B. The visual examinations are scheduled in Table A of Appendix A. Acceptance criteria for these examinations is covered in Section 13.0, Acce tance Criteria.

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 QMP-110.5, N-GP-7, and N-VT-1.

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1/3-SI-4.6.G Page 26 7.0 COMPONENTS SUBJECT TO EXAMINATION TVA CLASS 1 (continued) 7.5 Recirculation Pum s (2) 7.5.1 Recirculation Pum Casin The recirculation pump casings have no seam welds. The casings are cast stainless, steel, ASTM A-351, GR CF8M.

There is a requirement for visual examination of the pump internal pressure boundary surfaces when the pump is disassembled during the 10-year interval.

Disassembly of the pump is in accordance with MMI-21 and provides for the examinations listed. See Table A of Appendix A for scheduled examinations (see RFR ISI-4).

7.5.2 Recirculation Pum Casin Boltin There are 16 pump casing studs (ASTM A-540, GR B23) on each of the two pumps. All the casing studs on each pump shall be ultrasonically examined and the stud nuts (ASTM A-194, CL 2H) shall be visually examined during the inspection interval. The ligaments between threaded stud holes and threads in the base material shall be visually examined when the connection is disassembled.

The studs shall be given a magnetic particle examination when they are removed. Disassembly of the recirculation pump is in accordance with MMI-21 and provides for the examinations listed. See Table A of Appendix A for scheduled examinations.

7.5.3 Recirculation Pum Su orts There are 3 integrally welded supports on each pump casing. One support on each pump shall be given an ultrasonic examination, and all 6 supports shall be visually examined during the inspection interval. See Table A of Appendix A for scheduled examinations.

7.6 Valve Pressure Boundar Valve Bod Seam Welds The Unit .1 RWCU system valve FCV 69-1 has a valve body seam weld. The valve was installed and preservice tested during the Unit 1, Cycle 4, outage. The other valves in Class 1 piping systems within the scope of this program are of single-piece cast or forged construction.

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1/3-SI-4.6.G

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Page 27.

COMPONENTS SUBJECT TO EXAMINATION TVA CLASS 1 (continued) 7.6.2 Valve Bod Internals Valves subject to examination include those valves exceeding 4-inch nominal 'pipe size. The valve body internal pressure boundary surfaces of one valve out of each group of the same design, construction, manufacturing method, and manufacturer performing similar functions is required to be examined during the inspection interval. Appendix C, Table 1, provides a list of the valves and their respective group numbers.

Visual examinations of internal pressure boundary surfaces during routine maintenance is performed and documented under existing plant administrative procedures (see RFR ISI-5). The existing plant procedures are listed below:

MCI0.001.VLV001 Main Steam Isolation Valves MCI0.001.VLV002 Main Steam Relief Valves MMI-13 Main Steam Relief Valves MMI-51 CSSC Valve Maintenance The plant personnel responsible for the maintenance of the valves shall send a copy of the completed data sheet to the Section XI Programs and Planning for inclusion in the final ISI report. As an alternate inspection, if a valve from a particular classification has not been disassembled as the end of the inspection interval approaches, a case-by-case study shall be made to determine the practicality of disassembling a valve from one of the multiple units solely for visual examination. If necessary, RFR ISI-5 shall be revised at that time.

7.6.3 Valve Pressure-Retainin Boltin None of the Class 1 valve bonnet or flange bolting is 2 inches or larger. The bolting smaller than 2 inches shall all be visually examined during the inspection interval. There are 50 valves (on each unit) with bolting smaller than 2 inches. The examinations shall be distributed equally among the three 40-month cycles of the inspection interval. The valves are listed in Appendix C, Tables 1 and 2. See Table A of Appendix A for scheduled examinations.

7.7 Exem ted Com onents The components exempted from volumetric and surface examination shall be visually examined (VT-2) during system pressure tests in accordance with IMA-5000 and IMB-5000 of ASME Section XI (see Section 7.0). The pressure tests and VT-2 examinations are implemented by SSP-8.5.

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t 1/3-81-4.6.G Page 28 8.0 COMPONENTS SUBJECT TO EXAMINATION-TVACLASS 2 The Class 2 corn P onents to be examined for the ISI are outlined in the following paragraphs. Selection of areas for examination are in accordance with paragraph IWC-2411 and Table IWC-2520 of ASME Section XI.

t Components that are exempted from examination in accordance with IWC-1220 of ASME Section XI are discussed in Section 8.6 of this program.

Where the program specifies a percentage of the total length of weld is to be examined, the area(s) examined shall be physically marked on the component and documented in the examination report. Where a percentage is not referenced the entire length shall be examined.

Bolting two inches or less in diameter shall not be ultrasonically examined (see RFR ISI-14).

Examinations of Class 2 components began during the first 40-month cycle of the inspection interval on Unit 3 and began with the second 40-month cycle on Units 1 and 2.

8.1 RHR Heat Exchan ers (4 -RHR Hx 8.1.1 RHR Hx Circumferential Seam Welds There are two circumferential shell welds on each heat exchanger, each approximately 14 feet in length, totaling 28 feet or 112.feet for the four; two circumferential shell cover welds on each heat exchanger, each approximately 15 feet in length, totaling 30 feet or 120 feet for the four; and one bottom head flange weld on each heat exchanger approximately 2.75 feet in length or 11 feet for the four. A total of two welds, one shell weld and one bottom head flange weld, shall be ult'rasonically examined during the inspection interval. The examinations shall cover at least 20 percent of each circumferential weld selected for examination, uniformly distributed among three areas around the vessel circumference. See Table B of Appendix A for scheduled examinations.

The shell and shell cover sections are fabricated to A-515, GR.70. Flange sections are fabricated to A-105, GR.II.

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1/3-SI-4.6.G Page 29 8.0 COMPONENTS SUBJECT TO EXAMINATION-TVACLASS 2 (continued) 8.1.2 RHR Hx Nozzle Welds There are two nozzle-to-shell welds on each heat exchanger. The nozzle-to-shell welds are not accessible for examination because of a reinforcement ring covering the nozzle-to-shell weld (see RFR ISI-13). The alternate inspection shall be a surface examination of the reinforcement ring welds. A total of one reinforcement ring weld (weld to the nozzle and to the shell) from the four RHR heat exchangers shall be surface examined during the inspection interval. See Table B of Appendix A for scheduled examinations.

The reinforcement rings are fabricated to A-515, GR.70.

RHR Hx Su ort Attachments There are three integrally welded support attachments on each heat exchanger. A total of one support shall be surface examined during the inspection interval. The support selected for examination shall be located on a different RHR Hx than those selected for examination in accordance with Sections 8.1.1 and 8.1.2. See Table B of Appendix A for scheduled examinations.

The support attachments are fabricated to ASTM A-283 Gr.D or equal.

RHR Hx Pressure-Retainin Boltin Each heat exchanger has a shell-to-tube sheet flange connection that has 56 studs with nuts (1-3/8 inches) and a shell cover-to-shell flange connection that has 56 studs with nuts (1-1/2 inches). The bolting is less than two inches in diameter (see RFR ISI-14).

The studs and nuts are fabricated to A-193 Gr.B7 and A-194 Gr.2H, respectively.

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t 1/3-SI-4.6.G Page 30 8.0 COMPONENTS SUBJECT TO EXAMINATION-TVACLASS 2 (continued) 8.2 Pi in Pressure Boundar The areas to be examined include circumferential pipe welds, larger than 4 inches diameter, at structural discontinuities or within 3 pipe diameters of the centerline of rigid pipe anchors, longitudinal weld joints in pipe fittings; and branch connection weld joints, larger than 4 inches diameter. The welds are selected for examination using the streaming method, where possible.

8.2.1 Main Steam Pi in The Class 2 main steam piping welds are identified and located on drawings listed in Appendix B. The examinations for this inspection interval are scheduled in Table B of Appendix A.

8.2. 2 R~HR Pi in The Class 2 RHR piping welds are identified and located on drawings listed in Appendix B. The examinations for this inspection interval are scheduled in Table B of Appendix A.

8.2.3 Closed Coolin Mater The Class 2 closed cooling water piping welds are identified and located on drawings listed in Appendix B. The examinations for this inspection interval are scheduled in Table B of Appendix A.

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t 1/3-SI-4.6.G Page 3'1 8.0 COMPONENTS SUBJECT TO EXAMINATION-TVACLASS 2 (continued) 8.3 Pi in Pressure-Retainin Boltin The Class 2 piping flange bolting is located on each RHR pump discharge line. Each connection includes 24 studs (1 inch) and 48 nuts. The bolting is less than two inches in diameter (see RFR ISI-14). The studs and nuts are fabricated to A-193 Gr.B7 and A-194 Gr.2H, respectively.

8.4 Com onent Su orts 8.4.1 Inte rail Welded Su ort Attachments The Class 2 integral attachments are identified and located on the support location drawings identified in Appendix B. The surface examinations are scheduled in Table B of Appendix A. Four of the restraints cannot be fully examined (see RFR ISI-11).

8.4.2 Com onent Su orts The Class 2 supports are identified and located on the support location drawings identified in Appendix B. The visual examinations are scheduled in Table B of Appendix A. Acceptance criteria for these examinations is covered in Section 13.0, Acce tance Criteria.

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 QMP-110.5,'-GP-7, and N-VT-1.

8.5 8.5.1 RHR Pum Casin There are no seam welds in the RHR pump casings. The pump casing is fabricated to ASTM A-216, Gr.WCB.

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1/3-SI-4.6.G Page 32 8.0 COMPONENTS SUBJECT TO EXAMINATION-TVACLASS 2 (continued) 8.5.2 RHR Pum Casin Boltin There are 24 studs and nuts (l-l/4 inches) on each pump casing. The bolting is less than two inches in diameter (see RFR ISI-14).

The studs and nuts are fabricated to SA-193 Gr.B7 and SA-194 Gr.2H, respectively.

8.5.3 RHR Pum Su orts There are 4 accessible integrally welded supports on each pump casing. One support from one pump shall be given a surface examination, and all the supports on that pump shall be visually examined during the inspection interval. See Table B of Appendix A for scheduled examinations. The pump supports are fabricated to ASTM A-36.

8.6 Exem ted Com onents Components exempted by IWC-1220, ASME Section XI, shall be visually examined (VT-2) during system pressure tests in accordance with IWA-5000 and IWC-5000. The pressure tests and VT-2 examinations are implemented by SSP-8.5.

Exempted components are: a) components in systems where both the design pressure and temperature are equal to or less than 275 psig and 200 degrees F, respectively; b) components in systems or portions of systems, other than emergency core cooling systems, which do not function during normal reactor operation; c) components which perform an emergency core cooling function, provided the control of fluid chemistry of the contained fluid is verified by periodic sampling and test; and d) component connections, piping, and associated valves, and vessels '(and their supports), that are 4 inches nominal pipe size and smaller.

The boundaries of components exempted by a), b), or c) above for the core spray, HPCI, and RCIC systems are listed in Table F of Appendix A. Augmented examinations of welds and supports in these systems are performed per paragraph 20.12 as scheduled in Table B, paragraph J of Appendix A.

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t 1/3-SI-4.6.G Page 33 9.0 COMPONENTS SUBJECT TO EXAMINATION-TVACLASS 3 TVA Class 3 components shall be visually examined during system pressure tests in accordance with IWA-5000, IWD-2000, and IWD-5000. The pressure tests are implemented by SSP-8.5.

Component supports for components exceeding four-inch nominal pipe size whose structural integrity is relied upon to withstand design loads when the system function is required shall be visually examined to detect any loss of support capability, and evidence of inadequate restraint (Refer to Section 13.0).

The Class 3 component supports are identified and located on the component support location drawings identified in Appendix B. All component supports shall be visually examined each inspection cycle (every 3-1/3 years) as scheduled in Table E of Appendix A.

Unit 3 was the only unit at BFN required to'eet this requirement during the first 40-month inspection cycle. This requirement is applicable for all three units at the beginning of the 80-month inspection cycle (July 1, 1981).

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 GAMP-110.5, N-GP-7, and N-VT-l.

System pressure test and VT-2 examination requirements are included in the BFN pressure test program and SSP-8.5; 10.0 AUTHORIZED INSPECTOR (AI TVA shall have a contract with an AIA Agency in accordance with ASME Section XI for inservice examinations, repairs, and replacements of TVA Class 1, 2, and 3 (equivalent) components at BFN. The ANII shall verify, assure, or witness that code requirements have been met. He shall have the prerogative and authorization to require requalification of any operator or procedure when he has reason to believe the requirements are not being met. TVA shall provide access for the AI in accordance with IWA-2140 of ASME Section XI.

TVA's interface with the ANII for ISI, repairs, and replacements is defined in SSP-6.9 and SSP-6.10.

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t 1/3-SI-4.6.G Page 3'4 11.0 EXAMINATION METHODS Any nondestructive examination procedures shall meet the requirements stated in this section.

11.1 Visual Examination A visual examination is employed to provide a report of the general condition of the part, component, or surface to be examined, including such conditions as scratches, wear, cracks, corrosion or erosion on the surfaces, misalignment or movement of the part or component, or evidence of leaking.

Visual examination shall be conducted in accordance with Article 9,Section V of the ASME Code except that lighting shall be sufficient to resolve a 1/32 inch wide black line on an 18 percent neutral gray background.

11.2 Surface Examination 11.2.1 Ma netic Particle Magnetic particle examination shall be conducted in accordance with Article 7,Section V of the ASME Code.

11.2.2 Li uid Penetrant 0 11.3 Liquid penetrant examination shall accordance with Article 6, Section Volumetric Examination be conducted V of the ASME in Code.

Radiographic techniques, employing penetrating radiation such as x-rays, gamma rays, or thermalized neutrons, may be utilized with appropriate image recording devices such as photographic film or papers, electrostatic systems, direct-image orthicons, or image converters.

For radiographic examinations employing either x-ray equipment or radioactive isotopes and photographic films, the procedure shall be as specified in Article 2,Section V of the ASME Code.

11.3.2 Ultrasonic Ultrasonic examination shall be conducted in'ccordance with Article IWA-2232 of ASME Section XI 1986 Edition.

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1/3-SI-4.6.G Page 35 12.0 UALIFICATIONS OF NDE PERSONNEL Personnel performing NDE operations shall be qualified in accordance with IWA-2300 of ASME Section XI as specified in QMP 102.4.

13.0 ACCEPTANCE CRITERIA All acceptance standards for ASME Code Class 1, 2, and 3 (equivalent) components shall be in accordance with IWA-3000, IWB-3000, IWC-3000, or IWD-3000 of ASME Section ZI, except where ASME Section III or other construction code examinations are employed to satisfy ASME Section XI requirements.

14.0 REPAIRS AND REPLACEMENTS The repair and replacement program shall be in accordance with SSP-6.9.

All PSIs of pipe welds shall be in accordance with the 1977 Edition, Summer 1978 Addenda of ASME Section ZI, IWB-2200(c), Table IWB-2500-1, and Table IWC-2500-1 beginning on January 1, 1992 (

Reference:

RFRs ISI-10 and ISI-15). This shall differ from the inservice inspections (ISI) and should not have an effect on the ISI credit examinations. As a precaution for NDE personnel, the major areas of difference are:

The volume of weld ultrasonically examined for PSI shall be the inner 1/3 per Figures IWB-2500-8 and IWC-2520-7 (77S78). The volume examined for ISI shall be the full volume (thickness) per Tables IWB-2500 and IWC-2520 (74S75).

2. For B-J branch connection welds, the cutoff for volumetric examination shall be 2-inch NPS for PSI per Table IWB-2500-1 (77S78). The cutoff for volumetric examination for ISI shall be 6-inch NPS per Table IWB-2600 (74S75).

3. Surface examinations (MT or PT) shall be required as a part of all PSI examinations.

,15.0 PUMP AND VALVE TESTING Pump and valve testing shall be in accordance with SSP-8.6.

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t 1/3-SI-4.6.G Page 36 16.0 RECORDS AND REPORTS 16.1 Recordin and Re ort of Examinations A detailed report of all examinations'hall be prepared by the performing or responsible organization and should contain but not be limited to the following information:

Title Page Table of Contents Introduction The introduction should include the following. information: Plant, unit number, PSI or ISI and cycle number, systems, components and vessels examinations were performed on, organization examinations were performed by, dates examinations were performed, ASME Code of Record.

Summary The summary should include a brief description of the overall inspection.

Summary of Notifications The summary of notifications shall give a short summary of each notification report along with the indication discrepancy and its location.

It should also contain the final disposition including a reference to the corrective action taken and the date of completion.

IV. Scan Plan The Scan Plan shall give a detailed description of all areas subject to examination during the inspection. It should contain the following information: Examination'Area, Code Category, Weld Size, Reference Drawing, Examination Nethod, Procedure, Calibration Block, Examiner, Report Number, and Date of Examination.

V. A Summary of Personnel Certifications.

VI. Calibration Sheets.

VII. Examination Data Sheets.

VIII. Copy of the ISI Report as discussed in Section 16.2.

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1/3-SI-4.6.G Page 37 All procedures and equipment shall be identified sufficiently to permit duplication of the examination at a later date. This shall include initial calibration data for the equipment and any significant changes.

All required and pertinent information shall be recorded on the appropriate data sheets by the performing organization. When portions of the inspection work are contracted, a detailed report shall be submitted to TVA by the contractor with all pertinent and required information. TVA shall retain the original copies of all raw data taken.

M/N Engineering shall review and submit, the final report to the Plant Manager for review. Data Sheet 1 in Appendix F shall be completed and used as a cover sheet for the final report and to document the review process.

16.2 ISI Re ort for Class 1 and 2 Com onents The ISI Report for Class 1 and 2 components shall be submitted within 90 days after the completion of the ISI to the NRC Region II Office in accordance with IMA-6220, ASME Section XI via the Nuclear Technology and Licensing organization [Reference SSp-4.5).

The ISI report shall have a cover sheet providing the following information:

(1) Date of corporate offices

'2)

Name of owner and address (3) Name and address of nuclear generating plant in which the nuclear power unit is located (4) Name or number assigned to the nuclear power unit by TVA (5) Commercial operation date for unit 1084(207)

t 1/3-SI-4.6.G Page 38 16.0 RECORDS AND REPORTS (continued)

All reports shall have a summary providing the following information:

(1) National Board Number assigned by the manufacturer to the pressure vessel or component.

(2) Names of the components or parts of the components for which this is a record, including such information regarding size, capacity, material, location, and drawings as may aid accurate identification.

(3) Name of the manufacturer of the components or parts for which this is a record, including the manufacturer's component or part numbers and such information regarding the manufacturer's corporate office or manufacturing plant locations as may aid in gaining 'access to the manufacturer's records regarding the components or parts that the manufacturer is maintaining.

(4) Date of completion of the ISI; (5) Name or names of the Inspector(s) when required.

(6) Name and mailing address of the employer(s) of the Inspector(s).

(7) Abstract of examinations performed, conditions observed, corrective measures recommended and taken.

(8) Signature of Inspector, when required.

(9) Owner's data report for ISI, Form NIS-1 as shown in Appendix II of ASME Section XI.

M/N Engineering shall submit the ISI Report to the plant for retention as a quality assurance record in accordance with SSP-3.1. M/N Engineering shall maintain a copy of the report for information.

1084(207)

t 1/3-SI-4.6.G Page 39 16.0 RECORDS AND REPORTS (continued) 16.3 Records for Class 1 2 and 3 Com onents The following records shall be available for review:

(1) Examination Plans (2) Examination Results and Reports (3) Examination Methods and Procedures (4) Evaluation of Results (5) Corrective Actions and Repairs 16.4 Records of S stem Pressure Tests Records of the visual examinations conducted during system pressure tests as required by Sections 7.7, 8.6, and 9.0 of this program shall consist of but not be limited to an itemization of the number and location of leaks found in a system and the corrective actions taken.

17.0 INSPECTION REPORTS IRs) 17.1 Any corrective action required as a result of ISI examinations shall be handled in accordance with SSP-3.4.

17.2 An IR 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. M/N Engineering shall provide/coordinate dispositions for IRs in accordance with SSP-3.1.

17.3 Existing NOI's (Notices of Indication) that were submitted to Technical Support for disposition, shall be closed upon rework and/or reexamination. A copy shall be filed with the original examination report.

1084(207)

t 1/3-SI-4.6.0 Page 40 17.0 INSPECTION REPORTS IRs) (continued) 17.4 Additional Sam le Selection for CC-1 and CC-'2 IRs If it is determined that additional examinations are required, these examinations shall be performed during the same outage as the initial examinations. A sample is defined as those items (welds, areas, or parts) as described or intended in a particular examination category and item number and within the same system.

For component support samples, the additional examinations may also be limited to component supports within the same examination method '(VT3, and VT4). The initial sample is the sample scheduled for examination at a particular outage for Section XI credit.

17.4.1 Evaluation for First Additional Sam le A first additional sample shall be selected for those examinations performed in the initial sample that reveal indications exceeding the corresponding acceptance standards of IWX-3000 of ASME Section XI. The first additional sample shall include approximately the same number of items examined in the initial sample. The first additional sample shall be selected from the 10-year interval sample. The items selected should be from those items that have the longest service time from its previous inservice examinations.

If a system contains a sample within the same examination category and item number as the initial sample which had the indication and is not scheduled for examination this outage, this system sample shall be evaluated to determine if "it should be examined this outage to provide a representative sample from each system within a particular examination category and item number. This evaluation should consider, but is not limited to, the type of indication found in the initial sample and similar system design and operating parameters.

M/N Engineering shall submit the additional sample to the M 6 I representative for addition to the scan plan.

1084(207) .

t 1/3-SI-4.6.G Page 41 17.0 INSPECTION REPORTS IRs (continued) 17.4.2 Evaluation for Second Additional Sam le A second additional sample shall be selected for those examinations performed in the first additional sample that reveal indications exceeding the corresponding acceptance standards of IWX-3000 of ASME Section XI.

The second additional sample shall include all the remaining items of the 10-year interval sample not examined in the initial or first additional sample during this outage. If no items remain in the 10-year interval sample (e.g., Accelerated Field Weld Program) and indications were found in the first additional sample, a notification of sample results shall be made to NE as described in Section 17.2.3. The M/N Engineering shall submit the second additional sample to the M & I representative for addition to the scan plan.

17.4.3 Notification of Sam le Results to Site En ineerin After completion of the second additional sample examinations, ASME Section XI code requirements for additional examinations are complete. If examinations performed in the second additional sample reveal indications exceeding the corresponding acceptance standards of IWX-3000 of ASME Section XI, Site Engineering (SE) shall be notified. Site Engineering shall be notified to evaluate the indications and make recommendation(s) for further action, if needed, within this and/or other systems.

This notification shall be sent to the Site Engineering Manager by M/N Engineering for coordination with the applicable SE staff. Included in the notification should be a summary of the indications found," number of examinations and number of indications in each sample, type of examination performed, examination category and item number, copies of the IRs, and any other pertinent information.

1084(207)

1/3-SI-4.6.G Page 42 18.0 CALIBRATION BLOCKS Many of the basic calibration blocks used for examinations at BFN were fabricated to the 1971 Edition of ASME Section XI. These blocks shall continue to be used for ISI work (see RFR ISI-10).

The M/N Engineering personnel shall be responsible for storage and control of the calibration blocks onsite as required in Appendix I, I-3150, of ASME Section XI.

M & I shall prepare and retain as-built calibration block drawings.

19.0 RE UESTS FOR RELIEF RFRs)

Where TVA has determined that certain code requirements or examinations are impractical, TVA shall submit written RFRs to NRC with information to support the determinations and any proposed alternate examinations.

The impractical code requirements or examinations shall be identified in this program, and references to particular RFRs shall be included.

When impractical examination requirements are identified in the field, the M & I shall notify M/N Engineering such that the information may be included in this program, and RFRs may be prepared if necessary.

The RFRs are included in Appendix G. The current RFRs are ISI-2 through ISI-15. Those requiring alternate examination are ISI-5 through ISI-10, ISI-13, and ISI-15.

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

20.0 AUGMENTED EXAMINATIONS Augmented examinations are performed in addition to ASME Section XI Code requirements. The augmented examinations may be required by the NRC or be self-imposed by TVA. Typical sources include generic letters, IE Bulletins, technical specifications, vendor recommendations, and industry experience.

The responsible organization or owner shall have technical and administrative responsibili,ty for each augmented examination identified in this section. This responsibility shall include scheduling any examinations through M/N Engineering, tracking the status of examinations, and reporting completed examinations. Responsible organizations requesting inclusion of augmented examinations in this section shall submit a written request to the Lead M/N Engineer . The written request shall include specific details such as requirement source, 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 & I and M/N Engineering to facilitate nondestructive examination procedure preparation, establishment of training programs, and personnel familiarization.

1084(207)

t 1/3-SI-4.6.G Page 43 20.0 AUGMENTED EXAMINATIONS (continued)

Prior to each refuelin g outa g e, a meeting shall be'initiated by the M/N Engineering. Meeting attendees shall include the responsible organizations, M/N Engineering, and M & I. .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, 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 future actions such as changes in the frequency of examination.

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

20.1 Feedwater Nozzles 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 spargers shall be visually examined every fourth refueling outage (MMI-182). A liquid penetrant examination of the nozzle bore and inner radius is required every nine refueling cycles or within 135 startup/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 ISI Summary Report unless a special report 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.

20.2 Core S ra Pi in DPM BF76M7 superseded by NUREG-0313 in Section 20.10.

1084(207)

1/3-SI-4.6.G Page 44 20.0

~ AUGMENTED EXAMINATIONS (continued) 20.3

~ Core S ra S ar ers Responsible organization: Site Engineering. The augmented examination requirements of the core spray spargers is included in MMI-182, which implements IE Bulletin 80-13. The spargers shall be visually examined each refueling outage. Volumetric techniques may be used to evaluate any indications. The reporting criteria is listed in MMI-182. If cra'cks are detected, the NRC onsite inspector and the regional office shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A written report of the examinations is to be sent to the NRC within 30 days of completion of the examinations.

20.4 Recirculation Pressure Test Connections The requirement for this examination has been superseded by Generic Letter 88-01 and NUREG-0313, Rev. 2 (see Section 20.16).

20.5 Jet Pum Assemblies and Holddown Beam Unit 3 Responsible organization: Site Engineering. The augmented examination requirements of the jet pump assemblies are included in MMI-182, which implements IE Bulletin 80-07. Each jet pump assembly shall be visually examined each refueling outage per these requirements. The jet pump holddown beams shall all be ultrasonically examined each refueling outage. The ultrasonic examination shall be performed using General Electric Procedure TP-508 0642 (Rev. A) or equal. Unit 3 is the only unit where the holddown beams have not been replaced.

The NRC regional office is to be promptly notified following completion of the inspection and a report issued to the NRC within 14 days.

1084(207)

t 1/3-SI-4.6.G Page 45 20.0 AUGMENTED EXAMINATIONS (continued) 20.6 CRD Return Line Reroute Responsible organization: Site Engineering. The augmented examination requirements of the CRD return line reroute are included in NUREG-0619. The requirements are a final liquid penetrant examination of the capped nozzle after the modification.

Also, the welded connections joining the rerouted CRD return line to the reactor water cleanup system shall be ultrasonically examined for three consecutive refueling outages. The weld RCRD-X-45 (X is unit number 1, 2, or 3) shall be ultrasonically examined, including the base metal on each side within one wall thickness (nominal wall .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. fields RCRDS-X-3 and RCRD-X-44 shall be ultrasonically examined along with the pipe on the downstream side. The refueling cycles for each unit to be examined are:

Cycle 4, Cycle 5, and Cycle 6.

Reporting is required within 6 months of completing an outage during which an inspection was performed. Refer to NUREG-0619, Section 8.3 for information to be included.

20.7 Reactor Mater Cleanu The requirement for this examination has been superseded by Generic Letter 88-01 and NUREG-0313, Rev. 2 (see Section 20.16).

20.8 Evaluation of Corrosion Dama e of Pi in Com onents Ex osed to Residue from the March 22 1975 Fire - Unit 1 Responsible organization: Site Engineering. The augmented examination requirements of piping components exposed to residue from the March 22, 1975 fire were included in MMI-53 for the first, second, third, and fourth refueling outages. MMI-46 includes the requirements for the sixth refueling outage. The performance and documentation of the examinations shall be the responsibility of the M/N Engineering . The metallurgical analysis required shall be the responsibility of Nuclear Engineering.

The examination of the Unit 1 piping components exposed to residue from the March 22, 1975 fire is a technical specification requirement (4.6.G.3).

A report is required each outage upon completion of the examinations. The data sheet is included in the instruction.

1084(207)

t 1/3-SI-4.6.G Page 46 20.0 AUGMENTED EXAMINATIONS (continued) 20.9 CRD Scram Dischar e Volume Responsible organization: Site Engineering. The augmented examination requirements of the Scram Discharge Volume (SDV) piping are included in NUREG-0803. The SDV piping shall be examined in accordance with the requirements of ASME Section XI Class 2 components. The inservice examinations of the SDV piping shall begin during the second cycle of the first inspection interval. See Table B of Appendix A for weld size and scheduled examinations. Results to be included with the final report (see Section 16.0).

20.10 NUREG-0313 Revision 1" The requirement for this examination has been superseded by Generic Letter 88-01 and NUREG-0313; Revision 2 (see Section 20.16).

20.11 Au mented Examinations in Lieu of Penetration Flued Head Meld Examination Responsible organization: M/N Engineering. To supplement RFR ISI-7, NRC requires that the first pressure boundary weld outside containment be ultrasonically examined for the penetrations listed in the RFR. The welds to be examined during the first 10-year inspection interval are:

Feedwater (Units 1 and 3): GFM-19 and GFM-2 Main Steam (Units 1 and 3): GMS-1, GMS-27, GMS-9, and GMS-18 RHR (Unit 1): DRHR-1-3, TRHR-1-194, DRHR-1-12, and TRHR-1-454A (Unit 3): DRHR-3-3, TRHR-3-194, DRHR-3-12, and TRHR-3-455A Core Spray (Units 1 and 3): DCS-3 and DCS-12 RMCU (Unit 1): DRWC-1-4E (Unit 3): DRWC-3-5A Results to be included with the final report (see Section 16.0).

1084(207)

t 1/3-SI-4.6.G Page 47 20.0 AUGMENTED EXAMINATIONS (continued) 20.12 Ten Percent Sam le of Class 2 Chemical Sam lin Exem ted Pi in Responsible organization: M/N Engineering. Ten percent of the code required examinations'hall be performed on the Class 2 portions of core spray, RCIC, and HPCI that were initially exempted by chemical sampling and pressure-temperature considerations.

The welds and supports for these systems are identified and located on drawings in Appendix B. The examinations for these systems are scheduled in Table B, paragraph J of Appendix A.

Results of examinations to be included with the final report (see Section 16.0).

20.13 Au mented Examination of Recirculation Inlet Safe-Ends The requirement for this examination has been superseded by Generic Lettei 88-01 and NUREG-0313, Revision 2 (see Section 20.16).

20.14 HPCI Pum Dischar e Su ort Ins ection Followin In'ection Responsible organization: Site Engineering. The augmented examination of the supports on the HPCI pump discharge line is imposed by TVA memorandum from G. T. Jones to G. R. Hall and J. R. Pittman (R35 841025 878). Each support from the HPCI pump (including the HPCI turbine and pump pedestals) to the steam tunnel penetration shall be visually examined after each injection. The SQO shall be notified to perform the examinations as required by the scram report.

This examination shall be performed in accordance with QMP 110.5 (formerly DPM N80E3) procedure N-VT-1 within three days following the injection. The report is to be submitted with the final report following the next scheduled refueling outage (see Section 16.0).

The supports to be examined are listed below:

Unit I: HPCIH-1-1, HPCIH-1-2, HPCIH-1-3, H-40, R-7, H-41, H-42, R-8, H-43, H-45, R-P, 8-5, H-6, H-7, H-8, R-IC, H-IC, H-ll, and H-12 (drawing ISI-0092-C).

Unit 3: HPCIH-3-19 HPCIH-3-2, HPCIH-3-39 H-1339 H-1329 H-1319 H-130, R-34, H-134, H-129, H-128, H-75, H-76, H-77, R-24, H-79, and H-80 (drawing CHM-2413-C).

1084(207)

1/3-SI-4.6.G Page 48 I

20.0 AUGMENTED EXAMINATIONS (continued) 20.15 Au mented Examination of Stainless and Dissimilar Metal Welds Susce tible to IGSCC (U.S. NRC Generic Letter 84-11)

The requirement for this examination has been superseded by Generic Letter 88-01 and NUREG-0313, Revision '2 (see Section 20.16).

20.16 Au mented Examination of Austenitic Stainless Steel and Dissimilar Metal Welds Susce tible to IGSCC Generic Letter 88-01 and NUREG-0313 Revision 2)

Responsible organization: Project Management. Austenitic stainless steel and dissimilar metal circumferential welds in piping four inches or larger in nominal pipe diameter which contain reactor coolant at a temperature above 200 degrees F during power operation shall be examined in accordance with the requirements of Generic Letter 88-01 and NUREG-0313, Revision 2.

Sample expansion shall be in accordance with Generic Letter 88-01 based on the IGSCC Category (A, B, C, or E) as defined in the generic letter. The welds requiring examination per this paragraph are listed in Table D of Appendix A by IGSCC category.

(Unit 1 Table D-l, and Unit 3 - Table D-3).

In addition to Section 11.0, Examination Methods, the examination procedures used for IGSCC examinations shall meet the requirements of Generic Letter 88-01. In addition to Section 12.0, Qualifications of NDE Personnel, personnel shall be qualified by the program described in Generic Letter 88-01 for performing IGSCC examinations.

1084(207)

1/3-SI-4.6.G Page 49' 20.0 AUGMENTED EXAMINATIONS (continued)

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.

F 100 percent every refueling outage.

G 100 percent during current outage.*

• IGSCC category' welds that are inaccessible for UT examination shall be replaced, corrosion resistant clad on the inside diameter or have local leak detection applied during Cycle 6 for Unit 1 and Cycle 5B for Unit 3.

Any flaws identified that do not meet the IMB-3500 cri.teria 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.

1084(207)

1/3-SI-4.6.G Page 50 20.0 AUGMENTED EXAMINATIONS (continued) 20.17 Reactor Vessel Interior Examinations Responsible organization: Project Management. In addition to the code required ISI examinations in Section 7.1.8, the following augmented examinations shall be performed at or near the end of the inspection interval unless a different frequency is specified.

20.17.1 Feedwater Nozzles, NUREG-0619, Section 20.1.

20.17.2 Core Spray Sparger, NRC IE Bulletin 80-13, Section 20.3.

20.17.3 T-box to Thermal Sleeve Weld Joint per GE SIL No. 289.

20.17.4 IRM/SRM Dry Tubes per GE SIL No. 409.

20.17.5 Jet Pump Sensing Line Brackets per GE SIL No. 420.

20.17.6 [NRC/C] Old Design Shroud Head Bolts per GE SIL No. 432 (ultrasonic examination) [NRC 86-0326-224].

20.17.7 Jet Pump Assemblies per IE Bulletin 80-07.

20.17.8 Shroud Support Access Hole Covers per GE SIL No. 462.

20.18 RPV Shell Weld Examination Responsible organization: M/N Engineering. The RPV shell welds, Examination Category B-A, Item Nos. Bl.ll and Bl.12 shall be examined for Unit 3 in outage Cycle 5B and for Unit 1 in outage Cycle 6 in accordance with the guidance of 10 CFR 50.55a(g)(6)(ii)(A) per TVA's commitment to the NRC dated September 27, 1991 (R08 910927 826).

TVA shall take ASME Section XI credit for these examinations as satisfying the requirements of Tables IWB-2500 and IWB-2600. A report of these examinations shall be included with the ISI Summary Report.

1084 (207)

t 1/3-SI-4.6.G Page 51

21.0 REFERENCES

21.1 ASME Boiler and Pressure Vessel Code, Section XI, 1971 Edition with Addenda through Summer 1971 21.2 ASME Boiler and Pressure Vessel Code, Section XI, 1974 Edition with Addenda through Summer 1975 21.3 ASME Boiler and Pressure Vessel Code,Section XI, Appendix III, 1977 Edition with Addenda through Summer 1978 21.4 ASME Boiler and Pressure Vessel Code,Section V, Articles 2, 6, 7 and 9, 1974 Edition with Addenda through Summer 1975 21.5 ASME Boiler and Pressure Vessel Code,Section V, Articles 4 and 5, 1977 Edition with Addenda through Summer 1978 21.6 ASME Boiler and Pressure Vessel Code,Section XI, 1986 Edition 21.7 Safet Anal sis Re ort 21.7.1 Browns Ferry Nuclear Plant Final Safety Analysis Report 21.8 Technical S ecifications 21.8.1 Section 4.6.G, Structural Integrity 21.9 Site Standard Practices 21.9.1 SSP-3.1, Quality Assurance Program 21.9.2 SSP-3.4, Corrective Action 21.9.3 SSP-4.5, Regulatory Reporting Requirements 21.'9.4 SSP-6.1, Conduct of Maintenance 21 '.5 SSP-6.9, ASME Section XI Repair and Replacement Program 21.9.6 SSP-6.10, ASME Section XI Inservice Inspection Program 21.9.7 SSP-8.5, ASME Section XI System Pressure Test 21.9.8 SSP-8.6, ASME Section XI Pump and.Valve Inservice Testing 21.9.9 SSP-9.3, Plant Modifications and Design Change Control 1084(207)

t 1/3-SI-4.6.G Page 52

21.0 REFERENCES

(continued) 21.10 TVA Nuclear ualit Assurance 21.10.1 QMP 102.4, Qualification and Certification Requirements for NQA NDE Personnel 21.10.2 QMP 110.5, Nondestructive Examination Procedures Approved for use on CSSC Items at all Nuclear Plants 21.11 Surveillance Instruction 1 2 3-SI-4.6.H.1 Visual Examination of H draulic and Mechanical Snubbers 21.12 Mechanical Maintenance Instructions 21.12.1 MCI0.001.VLV001, Main Steam Isolation Valves Atwood Morrill Co. Disassembly, Inspection, Rework, and Reassembly 21.12.2 MCI0.001.VLV002, Main Steam Relief Valves Target Rock Model 7567 Disassembly, Inspection, Rework, and Reassembly 21.12.3 MMI-1, Reactor Vessel and Cavity Disassembly and Reassembly 21.12.4 MMI-13, Main Steam Relief Valves 21.12.5 MMI-21, Reactor Recirculation Pump Rotating Assembly, Removal, and Replacement 21.12.6 MMI-46, Liquid Penetrant Examination of Piping and Piping Components Which Were Exposed to Residue from Plant Fire Unit 1 and 2 21.12.7 MMI-51, Maintenance of CSSC/Non-CSSC Valves and Flanges Units 1, 2, and 3 21.12.8 MMI-182, Reactor Vessel Internals Visual and Ultrasonic

,Inspection Units 1, 2, and 3 21.13 10 CFR Part 50 50.55a 1084(207)

1/3-SI-4.6.G Page 53 21.0

~ REFERENCES (continued) 21.14

~ NRC Documents 21.14.1 Generic Letter 88-01, NRC Position on IGSGC in BWR Austenitic Stainless Steel Piping 21.14.2 IE Bulletin 80-07, BWR Jet Pump Assembly Failure 21.14.3 NUREG-0312, BWR Feedwater Nozzle Examinations 21.14.4 NUREG-'0313, Rev. 2, Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping 21.14.5 NUREG-0619, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking 21.14.6 NUREG-0803, Generic Safety Evaluation Report Regarding Integrity of BWR Scram System Piping 21.15 General Electric Procedure TP-5080642, Rev. A, Jet Pump Beam Ultrasonic Examination 21.16 General Electric Service Instruction Letters 21.16.1 GE SIL No. 289, Core Spray Piping Visual Examination 21.16.2 GE SIL No. 409, Incore Dry Tube Cracks 21.16.3 GE SIL No. 420, Inspections of Jet Pump Sensing Lines 21.16.4 GE SIL No. 432, Shroud Head Bolt Cracks 21.16.5 GE SIL No. 462, Shroud Support Access Hole Cover Cracks 21.17 Vendor Manuals 21.17.1 BFN-VTM-B014-0010, B&W Reactor Pressure Vessel Manual, Contract 66060-90744 21.17.2 BFN-VTM-B580-0010, B&J Recirculation Pump Manual, Contract 67C60-91750 21.17.3 BFN-VTM-B260-0030, Bingham Pump Co. RHR Pump Manual, Contract 66C60-90744 21.17.4 BFN-VTM-P160-0010, VTM-P160-0010, Vendor Technical Manual for Perfex Corp. Heat Exchangers, Types NEN, CEU, CES, and CEN END OF TEXT 1084(207)

1/3-SI-4.6.G Page 54 APPENDIX A EXANINATION SCHEDULE 1084 (207)

1/3-SI-4.6.G Page 55 TABLE A (UNIT 1)

BROHNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam Com onents ~Sam le ~Sam le o~f Ins Month Month Month ~Cate or Remarks A. Reactor Vessel

l. Seam welds not in Core Region

a. Circumferential 15.2 ft. 15.2 ft. UT 2 ft. 2 ft. 11.2 ft. B-B CHM-0992-C

b. Longitudinal 13 ft. 13 ft. UT 1.1 ft. 2.1 ft. 9.8 ft. B-B CHM-1095-A Sheet 1

2. Closure Head Seam Hel d 8 ft. 2 ft. UT .5 ft..s ft. 1 ft. B-B CHM-1095-A Sheet 5

3. Closure Head 24 ft. 6 ft. UT 2 ft. 3 ft. B-B CHM-1095-A Meridional Held

4. Vessel-to-Flange 69 ft. 69 ft. UT 21 ft. 23 ft. 25 ft. 8-C CHM-1095-A Circumferential Held Sheet 3

5. Head-to-Flange 66 ft. 66 ft. UT 21 ft. 22 ft. 23 ft B-C CHM-1095-A Circumferential Held Sheet 4

6. Primary Nozzles Main Steam (26") (N3)

a. Nozzle-to-Vessel 4 UT 8-D CHM-1094-A and Inside Radii . .-Sheet 1

b. Nozzle-to-Safe End 4 UT B-J Core Spray (10") (N5)

a. Nozzle-to-Vessel 2 UT 1 B-0 CHM-1094-A and Inside Radii Sheet 1

b. Nozzle-to-Safe End 2 UT, PT 1 B-F 1084(207)

TABLE A (UNIT 1, CONTINUED)

Page 56 I

1/3-SI-4.6.G BRONNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam 1e ~Sam le o~f Ins Month Month Month ~Cate or Remarks Feedwater (12") (N4)

a. Nozzle-to-Vessel 6 UT B-D CHM-1094-A and Inside Radii Sheet 1

b. Nozzle-to-Safe End 6 UT 8-3 Recirculation Inl et (12") (N2)

B-D CHM-1094-A

a. Nozzle-to-Vessel 10 10 UT 3 and Inside Radii Sheet 1

'b. Nozzle-to-Safe End 10 10 UT,PT 3 B-F Recirculation Outlet (28") (Nl)

Nozzle-to-Vessel UT 8-D CHM-1094-A

a. 2 1 and Inside Radii Sheet 2

b. Nozzle-to-Safe End 2 UT,PT 1 B-F Jet Pump Instr. (4") (N8)

B-D CHM-1094-A

a. Nozzle-to-Vessel 2 UT 1 and Inside Radii Sheet 3 Nozzle-to-Safe End UT,PT B.-F

b. 2 1 CRD Hydr'aulic Return (4") (N9)

Nozzle-to-Vessel UT B-D CHM-1094-A

a. 1 and Inside Radii Sheet 5 Nozzle-to-Safe End UT,PT B-F

b. 1 1084(207)

1/3-SI-4.6.G Page 57 TABLE A (UNIT 1, CONTINUED)

BRONNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam le ~Sam 'le o~f Ins Honth Honth Honth ~Cate or Remarks Head Instr. (6") (N6) CHM-2102-A

a. Nozzle-to-Vessel 2 UT 8-D CHM-1094-A and Inside Radii Sheet 6

b. Nozzle-to-Flange UT 8-3 Head Vent (4") (N7) CHM-2102-A

a. Nozzle-to-Vessel UT 8-D CHM-.1094-A and Inside Radii Sheet 7

b. Nozzle-to-Flange UT

7. Closure Nuts 92 92 MT,UT 30 30 32 8-G-1 'HM-2001-C

8. Closure Studs 92 92 UT 30 30 32 8-G-1 4 4 MT 4 8-G-1 See Section 7.1.3

9. Closure Washers 92 92 VT 30 30 32 8-G-1 and Bushings 4 VT 4 8-G-1 See Section 7.1.3

10. Ligaments between 92 92 UT 30 30 32 8-G-1 See Section Threaded Stud Holes 7.1.3

11. CRD Housing Helds 40 40 VT Inspection During 8-0 Request. for System Pressure Tests Relief ISI-6

12. Vessel Penetrations 63 63 VT Inspection During 8-E System Pressure Tests

13. Support Skirt Held 4 ft. 4 ft. UT 2 ft. 2. ft. 8-H CHM-1091-.A

14. Vessel Cladding 6 6 VT 2 2 8-I-1 patches patches 1084(207)

1/3-SI-4.6. G Page 58 TABLE A (UNIT 1, CONTINUED)

BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam le ~Sam le ~of Ins Honth Honth Honth ~Cate or Remarks

15. Internals VT General Surveillance B-N-1, BF HMI-182 B-N-2 B. Piping Recirculation CHM-1081-C Ci rcumf erenti al 28" SS 31 UT B-3 22" SS 10 UT B-3 12" SS 30 UT B-J 4" SS 1 UT B-3 Recirculation Branch Pipe Connection Welds 12" SS UT B-3 4" SS PT B-J

2. Main Steam CHM;1082-C Circumferential 26" CS* 54 14 UT B-3 26" CS (Pipe Whip) 6 6 UT B-3 See Table C 6" CS 50 13 UT B-3 Branch Pipe Connection Welds 10" CS 1 UT 1 B-J 6" CS 25 PT or HT 2 8-J 3" CS 1 PT or MT B-3

• Four welds inaccessible: KMS-1-1, KHS-1-29, KHS-1-56, and KHS-1-81, see Request for, Relief ISI-7.

1084(207)

1/3-SI-4.6.G Page 59 TABLE A (UNIT 1, CONTINUED)

BRONNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam le ~Sam le ~of lns Month Month Month ~Cate or Remarks

3. Feedwater CHH-1080-C Circumferential 24" CS* 25 6 UT 8-3 20" CS 7 2 UT 8-J 12" CS 26 7 UT 8-3 12" CS (Pipe Hhip) 10 10 UT 8-3 See Table C Branch Pipe Connection Nelds 16" CS UT 8-3 8" CS UT 8-3

4. Core Spray CHH-1089-C Circumferential 10" 4 UT 8-3 12" 23 UT 8-3

5. RHR CHH-1088-C Circumferential 24" SS 18 UT 1 8-3 24" SS (Pipe Nhip) 1 UT 1 8-3 See Tabl e C 20" SS 4 UT 1 8-3 20" Dissimilar 1 UT, PT 1 8-F 20" CS 2 UT 8-3

• Two welds inaccessible: KFH-1-4, KFH-1-22, see Request for Relief ISI-7.

1084(207)

1/3-SI-4.6.G Page 60 TABLE A (UNIT 1, CONTINUED)

BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam le ~Sam 1e ~of Ins Month Month Month ~Cate or Remarks .

6. CRD Hydraulic Return CHM-1097-C Circumferential 8" CS 1' UT 1 B-3 6" CS UT B-3 4" CS UT B-3 4" Dissimilar 1 UT, PT B-F

7. RWCU CHM-1098-C Circumferential 8" CS UT B-3 6" SS UT B-3 6" SS (Pipe Whip) UT 2- B-3 See Table C 4" CS UT B-3

8. RCIC CHM-1098-C Circumferential 6" CS UT B-J

9. HPCI CHM-1099-C Circumferential 16" CS 1 1 UT B-J 14" CS 3 1 UT B-J 10" CS 12 2 ~

UT B-3 10" CS (Pipe Whip) 4 4 UT B-3 See Table C

10. Pressure Retaining 17 17 VT B-G-2 Bolting 1084(207)

~ '

1/3-SI-4.6.G Page 61 TABLE A (UNIT 1, CONTINUED)

BRONNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam le ~Sam le ~of lns Month Month Month ~Cate or Remarks ll. Pipe and Valve

.Component Supports

a. Integral y1 He 1 ded 101 (104*) 25 HT or PT 8 B-K-1 Appendix E Request for Relief ISI-9

b. Support Components . 122(117*) 122 VT .35 39 48 B-K-2 C. Recirculation Pum s

1. Pressure Retaining 32 . 32 VT, UT 10 10 12 B-G-1 Studs HT Nhen Removed Nuts 32 VT 10 10 12 B-G-1

2. Ligaments Between 32 32 VT Nhen connection 8-G-1 is disassembled

3. Integrally Helded UT- 8-K-1 Request for Supports VT B-K-2 Relief ISI-9

4. Pump Casing VT During Normal 8-L-2 Request for Maintenance Rel i ef ISI-4 D. Valves

1. Val ve Bodi es

a. Visual 60 VT During Normal B-H-2 Request for-Internals Maintenance Relief ISI-5

• Change in numbers due to modifications leading to Unit 2 restart.

1084(207)

0 1/3-SI-4.6.G Page 62 TABLE A (UNIT 1, CONTINUED)

BRONNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam le ~Sam le ~of lns Month Month Month ~Cate or Remarks

b. Valve Body Helds 1 UT B-H-1

2. Pressure Retaining 52 52 VT 17 16 19 B-G-2

~

Bolting E. Exempt Components VT Inspection During B-P See Hydrostatic Testing Section 7.7 1084(207)

1/3-SI-4.6.G Page 63 TABLE B (UNIT 1)

BRONNS FERRY NUCLEAR 'PLANT CLASS 2 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents '~Sam le ~Sam le o~f Ins Month Month Month ~Cate or Remarks A. RHR Heat Exchan ers CHM-2418-B

1. Circumferential Nelds 12 ft. 3 ft. UT 1 ft. 1 ft. 1 ft. C-A Bottom Head

.5 ft. .5 ft. UT .5 ft. C-A Flg. Held (RHRG-ll)

2. Nozzle-to-Vessel. MT or PT C-8 Request for Helds Rel i ef ISI-13

3. Integral y1 Nel ded MT or PT C-C Supports B. Main Steam Pi in CHM-2690-C

1. Circumferential Nelds 26" CS 2 UT C-F 24" CS 1& UT C-F 18" CS 10 UT C-F 6" CS 28 UT C-F

2. Branch Pipe Connection Held 6" CS UT C-F 1084(207)

1/3-SI-4.6. G Page 64 TABLE B (UNIT 1, CONTINUED)

BROHNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 &0 120 Exam

~Com onents ~Sam le ~Sam le o~f Ins Month Month Month ~Cate or Remarks C. ~RHR Pi in ISI-0362-C

1. Circumferential Helds 30" CS 6 2 24" CS 44 ll UT C-F 20" CS 51 13 UT C-F CS

'8" 21 5 UT C-F 16" CS 6 1 UT C-F 14" CS 5, 1 UT C-F 12" CS 1 1 UT C-F 10" CS 6 2 UT C-F 6" CS 21 5 UT C-F D. Closed Coolin Hater ISI-0029-C

~Pi in

1. Circumferential Helds 8" CS UT C-G E. Scram Dischar e Volume ISI-0036-C Tank

1. Circumferential UT C-F Entire Held Hel ds F. Scram Dischar e Volume ISI-0036-C

~Pi in

1. Circumferential 14 UT C-F Helds 1084(207)

1/3-SI-4.6.G Page 65 TABLE B (UNIT 1, CONTINUED)

BROWNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam le ~Sam le ~of lns Month Month Month : ~Cate or Remarks G. Pi in and Valve Com onent Su orts

l. Integrally Welded 2.

Supports Support Components 110(116*) 28 211(242*) 211 PT VT or

'9 MT 9 96 10 86 C-E-1 C-E-2 Appendix Appendix E

E H. ~RHR Pum s ISI-0022-C

1. Integral y1 Wel ded Supports PT or MT C-E-1

2. Support Components VT 1 1 C-E-2 I. Exem t Com onents VT Inspection During Section 8.6 Hydrostatic Testing J. Au mented Ins ection ISI-0091-C Circumferential Welds 24"CS UT C-F Section 19.12 20"CS UT C-F 16"CS UT C-F 14"CS UT C-F 12"CS UT C-F 10"CS UT C-F 8"CS UT C-F

• Change in number due to modifications leading to Unit 2 restart.

1084(207)

1/3-SI-4.6.G Page 66 TABLE B (UNIT 1, CONTINUED)

BROWNS FERRY NUCLEAR PLANT CLASS 2 COHPONENTS Quantity Inspected 40-Year 10-Year Hethod 40 80 120 Exam

~Com onents ~Sam 1e ~Sam le ~of Ins Honth Month Honth ~Cate or Remarks

2. RCIC Piping ISI-0093-C Circumf erenti al Section 19.12 Wel ds 12"CS UT C-F 10"CS UT C-F 8"CS UT C-F 6"CS UT C-F

3. Core Spray Piping ISI-0095-C Circumferential Section 19.12 Welds 16"CS 1 UT C-F 14"CS 1 UT C-F 12"CS 1 UT C-F 10"CS 0. UT C-F 12"SS 0 UT C-F

4. Integrally Welded Supports 44(38*) 5 HT or PT 1 C-E-1 Appendix E

5. Support Components 113(120*) 12 VT 4 C-E-2 Appendix E

• Change in numbers due to modifications leading to Unit 2 restart.

1084(207)

1/3-S I-4.6. G Page 67 TABLE A (UNIT 3)

BROHNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam le ~Sam le ~of lns Month Month Month ~Cate or Remarks A. Reactor Vessel

1. Seam Helds Not In Core Region a.

b.

Circumferential Longitudinal 15.2 13 ft.

ft. 15.2 13 ft.

ft. UT UT 2

1.6 ft.

ft.

2 2.1 ft..

ft.

11.2 ft.

9.3 ft.

B-B B-B ISI-0220-C CHM-1095-A Sheet 1

2. Closure Head Seam Held 8 ft. 2 ft. UT .5 ft..s ft. 1 ft. B-8 CHM-1095-A Sheet 5

3. Closure Head 24 ft. 6 ft. UT 2 ft. 2 ft. 2 ft. 8-B CHM-1095-A Meridional Held

4. Vessel-to-Flange CHM-1095-A Circumferential Held 69 ft. 69 ft. UT 23 ft. 23 ft. 23 ft. 8-C . Sheet 3

5. Head-to-Flange CHM-1095-A Circumferential Held 66 ft. 66 ft. UT 22 ft. 22 ft. 22 ft. 8-C Sheet 4

6. Primary Nozzl es

~

Main Steam (26") (N3)

a. Nozzle-to-Vessel UT B-D CHM-1094-A and Inside Radii Sheet 1

b. Nozzle-to-Safe End UT B-3 Core Spray (10") (N5)

- a. Nozzle-to-Vessel UT B-0 CHM-1094-.A and Inside Radii Sheet 1

b. Nozzle-to-Safe End UT, PT 1 B-F 1084(207)

1/3-S I-4.6. G Page 68 TABLE A (UNIT 3, CONTINUED)

BRONNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam 1e ~Sam le ~of Ins Month Month Month ~Cate or Remarks Feedwater (12") (N4)

a. Nozzle-to-Vessel 6 UT B-D CHM-1094-A and Inside Radii Sheet 1

b. Nozzle-to-Safe End 6 UT B-3 Recirculation Inl et CHM-1094-A (12" ) (N2) Sheet 1

a. Nozzle-to-Vessel 10 10 UT 3 B-D and Inside Radii

b. Nozzle-to-Safe End 10 10 UT, PT 3 B-F Recircul ation Outl et CHM-1094-A (28") (Nl) Sheet 1

a. Nozzle-to-Vessel 2 UT 1 B-D and Inside Radii

b. Nozzle-to-Safe End 2 UT, PT 1 8-F Jet Pump Instr. (4") (NB) CHM-1094-A Sheet 1

a. Nozzle-to-Vessel 2 UT 1 B-D and Inside Radii

b. Nozzle-to-Safe End 2 UT, PT 1 B-F ISI-0152-A CRD Hydraulic Return CHM-'1094-A (4") (N9) Sheet 5

a. Nozzle-to-Vessel 1 UT B-D and Inside Radii

b. Nozzle-to-Safe End 1 UT, PT B-F Head Instr. (6") (N6)

a. Nozzle-to-Vessel UT B-D CHM-1094-A and Inside Radii Sheet 6

b. Nozzle-to-Flange UT B-J 1084(207)

1/3-S I-4.6. G Page 69 TABLE A (UNIT 3, CONTINUED)

BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam le ~Sam le ~of.lns Month Month Month ~Cate or Remarks Head Vent (4") (N7)

a. Nozzle-to-Vessel UT 8-D CHM-1094-A and Inside Radii Sheet 7

b. Nozzle-to-Flange UT B-3

7. Closure Nuts 92 92 MT, UT 30 30 32 B-G-1 See Section 7.1.3

8. Closure Studs 92 92 UT 30 30 32 B-G-1 ISI-0267-C 4 4 MT 4 8-G-1 Closure Washers and 92 92 VT 30 30 32 B-G-1 See Section Bushings 4 4 VT 4 B-G-1 7.1.3

10. Ligaments Between 92 92 UT 30 30 . 32 8-G-1 Thread Stud Holes ll. CRD Housing Welds 40 40 VT Inspection During B-0 Request for Relief ISI-6 Hydrostatic Tests

12. Vessel Penetrations 63 63 VT Inspection During 8-E Hydrostatic Tests

13. Support Skirt To 4 ft. 4 ft. UT 1 ft, 1 ft. 2 ft. B-H CHM-1091-A Vessel Weld

14. Vessel Cladding 6 6 VT B-I-1 ISI-0317-A patches patches

15. Internals VT General Surveillance BN-1, BN-2 BF MMI-182.

1084(207)

1/3-SI-4.6. G Page 70 TABLE A (UNIT 3, CONTINUED)

BROWNS FERRY NUCLEAR PLANT CLASS 1 COHPONENTS Quantity Inspected 40-Year 10-Year Hethod 40 &0 120 Exam C~om onents ~Sam le ~Sam 1 e o~f. Ins Month Month Month C~ate or Remarks B. ~Pi in

1. Recirculation ISI-0328-C

a. Circumferential 28" SS 31 8. UT 8-3 22" SS 12 3 UT 8-3 12" SS 40 10 UT 8-3 4" SS 5 1 UT 8-3

b. Branch Pipe Connection Welds 1

21s 8 UT 8-3 4" SS 7 PT 8-J 2,. Hain Steam ISI-0329-C

a. Circumferential See Table C 26" CS 56* 14 UT 8-3 26" CS (Pipe Whip) 6" CS

b. Branch Pipe

'06 6 13 UT UT 8-3 8-3 Connection Welds 10" CS 1 UT 1 8-3 6" CS 25 PT, HT 2 2 2 8-J 3" CS 1 PT, HT B-3

• Four welds inaccessible: KHS-3-1, KHS-3-29, KHS-3-56, and KHS-3-81. See Request for Relief ISI-7.

1084(207)

1/3-SI-4.6.G Page 71 TABLE A (UNIT 3, CONTINUED)

BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam le ~Sam te ~of Ills Month Month Month ~Cate or Remarks

3. Feedwater ISI-0327-C

a. Circumferential 24" CS 27* 6 UT 8-3 20" CS 6 2 UT 8-3 12" CS 32* 8 UT 8-J 12" CS (Pipe Whip) 10 10 UT 8-3 See Table C 16" CS 1 UT 8-3 8" CS 1 UT 8-3

4. Core Spray IS I-0331-C

a. Circumferential 12" CS 2 UT 8-3 12" Di ssimi 1 ar 6 UT, PT 1 8-F 12" CS (Pipe Whip) 4 UT 2 8-3 Table C 10" Di ssimilar 2 UT, PT 1 8-F 10" CS 4 UT 8-3

5. RHR ISI-0330-C

a. Circumferential 24" SS 22 UT 2 8-J 24" SS (Pipe Whip) 3 UT 1 20" SS 7 UT 1 8-3 20" Dissimilar 1 UT, PT 1 8-F 20" CS 3 UT 8-J 6" Branch Connectionl 1 PT 8-J 6" Head Spray Deleted

• Eight welds inaccessible: KFW-3-4, -22, -40, -41, -42, -43, -44, and -45. See Request for Relief ISI-7.

1084(207)

1/3-SI-4.'6.G Page 72 TABLE A (UNIT 3, CONTINUED)

BROHNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam le ~Sam le o~ff ns Month Month Month ~Cate or Remarks

6. CRD Hydraulic Return IS I-0332-C

a. Circumferential 8" CS UT 8-J 6" CS UT B-3 4" CS UT B-3 4" Dissimilar UT, PT B-F

7. RHCU ISI-0332-'C &

a. Circumf erenti al ISI-0333-C 8" CS 2 UT 1 B-3 6" SS 12 UT B-3 6" SS (Pipe Whip) 4 UT 1 B-3 See Table C

[QA/Cl 4" CS 15 UT 8-3 4" DM 1 UT&PT 8-F 4" CS BC 1 MT 8-J ISI-0332-C

[PER BFPER920066]

a. Circumferential 6" CS UT 8-3

8. HPCI ISI-0333-C

a. Circumferential 16" CS 1 1 UT B-3 14" CS 3 1 UT 1 8-3 10" CS 10 2 UT 1 B-3 10" CS (Pipe Whip) 4 4 UT 1 B-3 See Table C

9. Pressure Retaining 17 17 VT B-G-2 Bolting

10. Pipe and Valve Component Supports

a. Integrally 101(106*) 25 MT or PT 7 B-K-1 Request for Welded Relief I.SI-9

• Change in numbers due to modifications leading to Unit 2 restart.

1/3-SI-4.6.G Page 73 TABLE A (UNIT 3, CONTINUED)

BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam C~om onents ~Sam le ~Sam le ~of Ins Month Month Month ~Cate or Remarks

b. Support 114* 114* VT 34 40 40 B-K-2 Components C. Recirculation Pum s

1. Pressure Retaining 32 32 VT, UT 10 10 12 B-G-1 Studs MT When Removed Nuts 32 32 VT 10 10 12 B-G-1

2. Ligaments Between 32 32 VT When Connection B-G-1 Threaded Stud Holes is Disassembled

3. Integrally Welded 6 2 UT 2 B-K-1 Request for Supports 6 VT 2 B-K-2 Relief ISI-9

4. Pump Casing VT During Normal B-L-2 Request for Maintenance Rel i ef ISI-4 D. Valves

1. Valve Bodies 60 VT During Normal B-M-2 Request for Maintenance Rel i ef ISI-5

2. Pressure Retaining 50 50 VT 24 19 8-G-2 Bolting E. Exem t Com onents VT Inspection During B-P See Hydrostatic Testing Section 7.7

• Change in numbers due to modifications leading to Unit 2 restart.

1084(207)

1/3-SI-4.6. G Page 74 TABLE B (UNIT 3)

BROHNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS guantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam 1e ~Sam le o~f Ins Month Month Month C~ate or Remarks A. RHR Heat Exchan ers ISI-0422-C ft. ft. ft. ft. ft.

1. Circumferential Helds 12

.5 ft..5 3 ft.

UT UT 1

.5 ft 1

1 C-A C-A Bottom Head Flg. Held (RHRG-11)

2. Nozzle to Vessel MT or PT C-8 Request for Helds Relief ISI-13

3. Integrally Helded MT or PT C-C Supports B. Main Steam Pi in ISI-0354-C

1. Circumferenti al Hel ds 26" CS 2 UT C-F 24" CS 18 UT C-F 18" CS 10 UT C-F 6" CS 28 UT C-F

2. Branch Pipe Connection Held 6" CS UT C-F 1084(207)

1/3-SI-4.6. G Page 75 TABLE B (UNIT 3, CONTINUED)

BROHNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam le ~Sam 1e o~f Ins Month Month Month ~Cate or Remarks C. ~RHR Pi in CHM-2406-C

1. Circumferential Helds 30" CS 6 1 UT 24" CS 44 10 'UT C-F 20" CS 52 14 UT G-F 18" CS 21 5 UT C-F 16" CS 6 2 UT C-F 14" CS 5 1 UT C-F 12" CS 1 1 UT C-F 10" CS 10 3 UT C-F 6" CS 20 4 UT C-F D. Closed Coolin Hater

~Pi in ISI-0033-C

1. Circumferential Welds 8" CS UT C-G E. Scram Dischar e Volume Tank ISI-0143-C

1. Circumferential Helds UT C-F Entire Held F. Scram Dischar e Volume

~Pi in ISI-0143-C

1. Circumferential Hel ds 14 UT C-F 1084(207)

1/3-SI-4.6. G Page 76 TABLE B (UNIT 3, CONTINUED)

BRONNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam le ~Sam le ~of Ins Month Month Month C~ate or Remarks G. Pi in and Valve Com onent Su orts

l. Integrally Nelded Supports 108(106*) 27 PT or MT 6 12 C-E-1 Appendix E,

2. Support Components '189(197*) 189 VT 46 75 68 C-E-2 H. ~RHR Pum s

1. Integral y1 Hei ded Supports PT or MT C-E-1 IS I-0311-B

2. Support Components 16 VT C-E-2 I. Exem t Com onents VT Inspection During Section 7.7 Hydrostatic Testing

3. Au mented Ins ection CHM-2407-C Circumferential Helds Section 19.12 24"CS 1 UT C-F 20"CS 3 UT C-F 16"CS 4 UT C-F 14"CS 5 UT C-F 12"SS 1 UT C-F 10"CS 5 UT C-F 8"CS 1 UT C-F

• Change in numbers due to modifications leading to Unit 2 restart.

1084(207) m ~

1/3-SI-4.6.G Page 77 TABLE B (UNIT 3, CONTINUED)

BROHNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam le ~Sam le ~of lns Month Month Month ~Cate or Remarks

2. RCIC Piping Circumferential Helds CHM-2408-C Section 19.12 12"CS UT C-F 10"CS UT C-F 8"CS UT C-F 6"CS UT C-F

3. Core Spray Piping Circumferential Helds IS I-0102-C Section 19.12 16 "CS 1 UT C-F 14"CS 1 UT C-F 12"CS 1 UT C-F 10"CS 0 UT C-F 12"SS 0 UT C-F

4. Integrally Helded Supports 45(43*) 5 MT or PT C-E-1 Appendix E

5. Support Components 127(125*) 13 VT C-E-2 Appendix E Chemical Exemption

• Change in numbers due to modifications leading to Unit 2 restart.

1084(207)

1/3-SI-4.6.G Page 78 TABLE C HELD INSPECTION FOR PIPE NHIP PROTECTION

~Sstem Held Identification Hain Steam GMS-32, GMS-15, GHS-24, GNS-6, KNS-104, KNS-24 Units 1 & 3 Feedwater KFH-39, GFH-15, KFH-38, GFH-9, GFH-12, KFH-13, GFW-26, KFH-31, GFH-29, GFH-32 Units 1 & 3 RHR Unit l. DSRHR-8A, DSRHR-7, DSRHR-4 Unit 3 DSRHR-4, DSRHR-6, DSRHR-7 Core Spray Unit 1 DSCS-12, DSCS-4, DSCS-11, DSCS-5 Unit 3 TSCS-407, TSCS-408, TSCS-423, TSCS-424 RHCU Units 1 & 3 DSRNC-4, DSRHC-6, DSRHC-3, DSRHC-5 HPCI Unit 1 THPCI-154, THPCI-152, THPCI-153, THPCI-153B Unit 3 THPCI-72, THPCI-70, THPCI-71, THPCI-70A NOTE: 100'X of the pipe whip protection welds must be examined each interval per Technical Specification 4.6.G.

1084(207)

1/3-SI-4.6.G Page 79 APPENDIX A TABLE D 1A UNIT 1 MELDS RE UIRED TO BE EXAMINED PER GENERIC LETTER 88-01 MELD PIPE SIZE MELD IGSCC EXAN NUMBER SYSTEH ~(INGHES CONFIG CATEGORY RCRD-1-49 CRD 4 E, V D DCS-1-04 CS 12 P, P D DCS-1-05 CS 12 P, V D DCS-1-06 CS 10 E, V D DCS-1-09 CS 12 P, SE D DCS-1-14 CS 12 P, V D DCS-1-15 CS 12 E, V D DCS-1-16 CS 12 P, V D DCS-1-17 CS 12 E, V D DCS-1-18 CS 10 P, SE D DSCS-1-01 CS 12 E, P D DSCS-1-04 CS 12 E, P D DSCS-1-05 CS 12 E, P D DSCS-1-06 CS 10 E, P D DSCS-1-08 CS 12 E, P D DSCS-1-09 CS 10 P, P D DSCS-1-10 CS 12 E, P D DSCS-1-11 CS 12 E, P D DSCS-1-12 CS 12 E, V D DSCS-1-13 CS 10 E, P D GR-1-07 RECIR 4 C, P D GR-1-08 RECIR 28 D GR-1-09 RECIR 12 P, D GR-1-10 RECIR 12 E, D GR-1-12 RECIR 12 P, D "GR<<1-13 RECIR 12 E, P D GR-1-14 RECIR 12 P, SE D GR-1-15 RECIR 12 P, R D GR-1-16 RECIR 12 E, P D GR-1-17 RECIR 12 P, SE D GR-1-18 RECIR 22 H, X D GR-1-19 RECIR 12 P, S D GR-1-20 RECIR 12 E, P D GR-1-21 RECIR 12 P, SE D GR-1-22 RECIR 12 P, S D GR-1-23 RECIR 12 'D GR-1-24 RECIR 12 SE D 1084{207)

e 1/3-SI-4.6.G Page 80 APPENDIX A TABLE D-lA (Continued)

UNIT 1 WELDS RE UIRED TO BE EXAMINED PER GENERIC LETTER 88-01 WELD PIPE SIZE WELD IGSCC EXAM NUMBER SYSTEM ~INCHES) CONFIG CATEGORY GR-1-25 RECIR 22 H, V D GR-1-26 RECIR 22 H, V D GR-1-28 RECIR 28 Pi V D GR-1-29 RECIR 28 Ei V D GR-1-34 RECIR 28 ~

P, X D GR-1-35 RECIR 12 Pi S D GR-1-36 RECIR 12 E, P D GR-1-37 RECIR 12 Pi SE D GR-1-38 RECIR 12 Pi S D GR-1-39 RECIR 12 E, P D GR-1-40 RECIR 12 Pi SE D GR-1-42 RECIR 12 E, P D GR-1-43 RECIR 12 Pi SE D GR-1-44 RECIR 22 H, X D GR-1-47 RECIR 12 Pi SE D GR-1-48 RECIR 12 Pi S D GR-1-49 RECIR 12 E, P D GR-1-50 RECIR 12 Pi SE D GR-1-51 RECIR 22 H, V D GR-1-52 RECIR 22 H, V D GR-1-53 RECIR 28 Pi SE D GR-1-55 RECIR 28 P, T . D GR-1-59 RECIR 28 Pi SE D GR-1-62 RECIR 28 Ei V D GR-1-63 RECIR 28 Pi V D KR-1-13 RECIR 12 BC D KR-1-17 RECIR 12 E, P D KR-1-19 RECIR 12 BC D KR-1-33 RECIR 22 R, X D KR-1-35 RECIR 12 BC D KR-1-38 RECIR 12 E, P D KR-1-39 RECIR 12 E, P D KR-1-40 RECIR 12 E, P D KR-1-41 RECIR 12 BC D KR-1-43 RECIR 12 E, P D KR-1-44 RECIR 12 E, P D KR-1-46 RECIR 28 P, T D KR-1-50 RECIR 28 Ei P D KR-1-51 RECIR 28 E, P D 1084(207)

1/3-81-4.6.G Page 81 APPENDIX A TABLE D-lA (Continued)

UNIT 1 WELDS RE UIRED TO BE EXAMINED PER GENERIC LETTER 88-01 WELD PIPE SIZE WELD IGSCC EXAM NUMBER SYSYEN (INCHES) CONFIG CATEGORY DRHR-1-02 RHR ~ 24 Pi V D DRHR-1-03 RHR 24 PEN, V D DRHR-1-06 RHR 24 Pi V D DRHR-1-07 RHR 24 Ei V D DRHR-1-09 RHR 24 P, T D DRHR-l-ll RHR 24 Pi V D DRHR-1-12 RHR 24 PEN% V D DRHR-1-13 RHR 24 E, P D DRHR-1-14 RHR 24 Ei V D DRHR-1-16 RHR 24 Ei V D DRHR-1-19 RHR 20 P, T D DRHR-1-21 RHR 20 Pi V D DRHR-1-22 RHR 20 Pi V D DSRHR-1-01 RHR 24 E, P D DSRHR-1-02 RHR 24 E, P D DSRHR-1-03 RHR 24 P, P D DSRHR-1-05A RHR 24 E, P D DSRHR-1-06 RHR 24 P, P D DSRHR-1-07 RHR 24 P, P D DSRHR-1-08 RHR 6 BC D TRHR-1-190 RHR 20 Ei V D TRHR-1-191 RHR 20 Ei V D JP-1-1A RPV 4 Ni SE D JP-1-1B RPV 4 Ni SE D N 1B-SE RPV 28 Ni SE D N 2A-SE RPV 12, Ni SE D N 2B-SE RPV 12 Ni SE D N 2C-SE RPV 12 Ni SE D N 2D-SE RPV 12 N, SE D N 2E-SE RPV 12 Ni SE D N 2F-SE RPV 12 Ni SE D N 2G-SE RPV 12 Ni SE D N 2H-SE RPV 12 Ni SE D N 2J-SE RPV 12 N, SE D N 2K-SE RPV 12 Ni SE D N 5A-SE RPV 10 N% SE D N 5B-SE RPV 10 Ni SE D 1084(207)

1/3-SI-4.6.G Page 82 APPENDIX A TABLE D-1A (Continued)

UNIT 1 WELDS RE UIRED TO BE EXANINED'PER GENERIC LETTER 88-01 WELD PIPE SIZE WELD IGSCC EXAt't NUMBER SYSTEM ~INCHES ) CONFIG CATEGORY DRMC-1-01 RWCU 6 Pi V DRWC-1-04E RMCU 6 P, PEN DSRWC-1-01AX RWCU 6 E, P DSRWC-1-02X RWCU 6 E, P DSRWC-1-03X RWCU 6 E, P DSRWC-1-04X RMCU 6 E, P DSRWC-1-05 RWCU 6 Ei P DSRWC-1-06 RWCU 6 E, P DSRWC-1-07 RWCU 6 E, P TRMC-1-01 RWCU 6 E, P TRMC-1-02X1 RMCU 6 Ei V TRMC-1-04 RWCU 6 TRWC-1-04A RWCU 6 P, P CS-1-69(OL) CS 12 OL/Pi DCS-1-07{OL) CS 12 OL/Pi DCS-1-08(OL) CS 12 OL/Ei GR-1-03(OL) RECIR 28 OL/Ei GR-1-27(OL) RECIR 28 OL/P, GR-1-41(OL) RECIR 12 OL/Pi GR-1-46(OL) RECIR 12 OL/E, GR-1-54(OL) RECIR 28 OL/Ei GR-1-56(OL) RECIR 28 OL/Ei V GR-1-57(OL) RECIR 28 OL/P, V E GR-1-58(OL) RECIR 28 OL/Ei P E GR-1-60{OL) RECIR 28 OL/E, P E GR-1-61(OL) RECIR '28 OL/Pi P GR-1-64(OL) RECIR 28 OL/Ei P KR-1-03(OL) RECIR 28 OL/Pi T KR-1-14(OL) RECIR 12 OL/BC KR-1-15(OL) RECIR 22 OL/Ci H KR-1-16(OL) RECIR 12 OL/Ei P KR-1-18(OL) RECIR 12 OL/Ei P KR-1-20(OL) RECIR 12 OL/BC KR-1-21(OL) RECIR 12 OL/Ei P KR-1-22 (OL) RECIR 12 OL/E, P KR-1-36(OL) RECIR 12 OL/BC KR-1-37(OL) RECIR 22 ~

OL/C, H KR-1-42(OL) RECIR 12 OL/BC KR-1-45(OL) RECIR 28 OL/Ei P KR-1-48(OL) RECIR 28 OL/Ei P KR-1-52(OL) RECIR 28 OL/Ei P 1084(207)

1/3-SI-4.6.G Page 83 APPENDIX A TABLE D-1A (Continued)

UNIT 1 WELDS RE UIRED TO BE EXAMINED PER GENERIC LETTER 88-01 WELD PIPE SIZE WELD IGSCC EXAM NUMBER SYSTEM ~(INCHES CONFIG CATEGORY DRHR-1-05(OL) RHR 24 OL/E% V E DRHR-1-08(OL) RHR 24 OL/P, V E DRHR-1-15(OL) RHR 24 OL/P, V E DRHR-1-17(OL) RHR 24 OL/P, V E DRHR-1-18(OL) RHR 24 OL/P, T E DRHR-1-20(OL) RHR 20 OL/E$ P E DSRHR-1-04(OL) RHR 24 OL/E, P E DSRHR-1-04A(OL) RHR 24 OL/E% E E DSRHR-1-05(OL) RHR 24 OL/E, P E DSRHR-1-08A(OL) RHR 24 OL/P% P E DSRHR-1-08B(OL) RHR 24 OL/E$ P E DSRHR-1-09(OL) RHR 20 OL/E% P E DSRHR-1-10(OL) RHR 20 OL/E$ P E DSRHR-1-11(OL) RHR 20 OL/E$ P E DRWC-1-01A(OL) RWCU 6 OL/P, V E GR-1-01 RECIR 28 P, P F GR-1-02 RECIR 28 P% V F GR-'1-45 RECIR 12 P% S F KR-1-02 RECIR 28 E, P F KR-1-12 RECIR 22 H, X F KR-1-24 RECIR 28 E, P F KR-1-25 RECIR 28 P, T F KR-1-34 RECIR 22 H, X F KR-1-47 RECIR 28 E, P F DRHR-1-04 RHR 24 E, P F 1084 (20 7)

1/3-81-4.6.G Page 84 APPENDIX A TABLE D-1A (Continued)

UNIT 1 WELDS RE UIRED TO BE EXAMINED 'PER GENERIC LETTER 88-01 WELD PIPE SIZE WELD IGSCC EXAM NUMBER SYSTEM ~INCHES CONFIG CATEGORY RCRD-1-50 CRD 4 E$ V G RCRD-1-52 CRD P, V G DCS-1-13 CS 12 P, P G DSCS-1-02 CS 12 E, P G DSCS-1-03 CS 12 E, P G DSCS-1-07 CS 12 Ei P G.

GR-1-04 RECIR 4 C$ P G GR-1-11 RECIR 12 P$ SE G GR-1-30 RECIR 4 C$ P G GR-1-33 RECIR 4 C$ P G GR-1-63A RECIR 4 F, F G GR-1-63B RECIR 4 BC G KR-1-01 RECIR 4 BC G KR-1-04 RECIR 4 BC G KR-1-11 RECIR 22 R, X t

G KR-1-23 RECIR 4 BC G KR-1-26 RECIR BC G KR-1-49 RECIR 4 BC G KR-1-53 RECIR 4 BC G DRHR-1-03B RHR 24 P, PEN G DRHR-1-13B RHR 24 ~ P, PEN G N 1A-SE RPV 28 N, SE G RCRD-1-33 RPV 4 C$ N G DSRWC-1-01B RWCU 6 P$ S G 1084(207)

1/3-SI-4.6.G Page 85 APPENDIX A TABLE D-1B UNIT 1 STAINLESS AND DISSIMILAR METAL WELDS NOT SUBJECT TO GENERIC LETTER 88-01 EXAMS WELO HIISKE CS-1-67 CS-1-68 XXSIEH CS CS 14 12 PIPE SIZE WELO LIKHKRL. 95EIG E,

V P

IGSCC EXAM AKGQEY N/A N/A ISI QEMQUi IS[-0095-C 02 IS[-0095-C 02 SHEET HLMKE TEMPERATURE EXCLUSION.

TEMPERATURE EXCLUSIONS OCS-1-01 CS 12 ED V N/A [5I-0095-C 01 TEMPERATURE EXCLUSION.

OC5-1-01A CS 14 E, E N/A ISI-0095-C 01 TEMPERATURE EXCLUSION.

OCS-1-02X CS 12 P, V N/A ISI-0095-C 01 TEMPERATURE EXCLUSION.

OCS-1-03 CS 12 PEN. V N/A CHM-1089-C 01 TEMPERATURE EXCLUSION.

OCS-I-04A CS 10 P, PEN N/A CHM-1089-C 01 TEMPERATURE EXCLUSION.

INACCESSIBLE IN PENETRATION X-16A.

OCS-I-'12 CS 12 PEN, Y N/A CHM-1089-C Ol TEMPERATURE EXCLUSION.

OCS-1-12A CS 12 P. PEN N/A CHM-I089-C 01 TEMPERATURE EXCLUSION.

INACCESSIBLE PENETRATION X-16B.

OSCS-1-14 CS 12 E, P N/A ISI-0095-C 01 TEMPERATURE EXCLUSION.

TCS-1-02A CS 12 P, P N/A ISI-0095-C 01 TEMPERATURE EXCLUSION.

SHPCI-1-1 HPCI 12 F, P N/A ISI-0091-C 02 TEMPERATURE EXCLUSION.

SHPC I-1-2 HPCI 12 E, P N/A ISI-0091-C 02 TEMPERATURE EXCLUSION.

SHPCI-1-3 HPCI 12 E, P N/A ISI-009'I-C 02 TEMPERATURE EXCLUSION.

SHPCI-1-4 HPCI 12 E, P N/A ISI-0091"C 02 TEMPERATURE EXCLUSION.

SHPCI-1-5 HPCI 12 E, F N/A ISI"0091-C 02 'EMPERATURE EXCLUSION.

OSRWC-1-04E RWCU 6 P, PEN N/A CHM-1098-C-01 INACCESSIBLE IN PENETRATION.

1084(207)

1/3-81-4.6.G Page 86 APPENDIX A TABLE D-3A UNIT 3 MELDS RE UIRED TO BE EXAMINED PER GENERIC LETTER 88-01 PIPE SIZE MELD IGSCC EXAN SYSTEM ~INCHES) CONFIG CATEGORY RMR-3-001-G003 RECIR 12 P, SE A RWR-3-001-G006 RECIR 12 P, SE A RMR-3-001-G009 RECIR 12 P, SE A RWR-3-001-G012 RECIR 12 P, SE A RWR-3-001-G015 RECIR 12 P, SE A RMR-3-001-G016 RECIR 12 P, P A RWR-3-001-G017 RECIR 12 P', RT A RWR-3-001-G018 RECIR 12 P, T A RWR-3-001-G019 RECIR 22 Ts X A RWR-3-001-G020 RECIR 12 P, T A RWR-3-001-G021 RECIR 22 Ts X A RWR-3-001-G022 RECIR 12 P, T A RWR-3-001-G023 RECIR 12 P, RT A RWR-3-001-G024 RECIR 12 P, P A RMR-3-001-G025 RECIR 28 P, T A RMR-3-002-G003 RECIR 12 P, SE A RWR-3-002-G006 RECIR 12 P, SE A RWR-3-002-G009 RECIR 12 P, SE A RWR-3-002-G012 RECIR 12 P, SE A RMR-3-002-G015 RECIR 12 P, SE A RMR-3-002-G016 RECIR 12 P, P A RWR-3-002-G017 RECIR 12 P, RT A RWR-3-002-'G018 RECIR 12 P, T A RWR-3-002-G019 RECIR 22 Ts X A RWR-3-002-G020 RECIR 12 P, X A RWR-3-002-G021 RECIR 22 Ts X A RWR-3-002-G022 RECIR 12 P, T A RWR-3-002-G023 RECIR 12 P, RT A RWR-3-002-G024 RECIR 12 P, P A RWR-3-002-G025 RECIR 28 P, T A SW-TPR-3-19 RECIR 28 Ts X A SM-TPR-3-21 RECIR 28 Ts X A RHR-3-002-G001 RHR 24 P, T A RHR-3-002-G002 RHR 24 P, V A RHR-3-002-G003 RHR 24 P, T A RHR-3-002-G004 RHR 24 P, V A 1084(207)

1/3-SI-4.6.G Page 87 APPENDIX A TABLE D-3A (ConLiaued)

UNIT 3 WELDS RE UIRED TO BE EXANINED PER GENERIC LETTER 88-01 WELD PIPE SIZE WELD IGSCC EXAM NUMBER SYSTEM ~INCHES ) CONFIG CATEGORY RWR-3-001-G001 RPV 12 N, SE A RWR-3-001-G004 RPV 12 N$ SE A RWR-3-001-G007 RPV 12 N, SE A RWR-3-001-G010 RPV 12 N$ SE A RWR-3-001-G013 RPV 12 N% SE A RWR-3-002-G001 RPV 12 N, SE A RWR-3-002-G004 RPV 12 N$ SE A RWR-3-002-G007 RPV 12 N% SE A RWR-3-002-G010 RPV 12 N% SE A RWR-3-002-G013 RPV 12 N$ SE A RWR-3-003-G001 RPV N, SE A RWR-3-003-G050 RPV N$ SE A RWCU-3-001-G001 RWCU P, PEN . A RWCU-3-001-G011 RWCU P% V A RWCU-3-001-G014 RWCU E, P A RWCU-3-001-G015 RWCU E, P A RWCU-3-001-G016 RWCU E, P A RWCU-3-001-G017 RMCU E, P A RWCU-3-001-G018 RWCU E, P A RWCU-3-001-G019 RMCU E, P A RWCU-3-001-G020 RWCU E, P A RWCU-3-001-G021 RWCU E, P A RWCU-3-001-G022 RWCU P$ V A RWCU-3-001-G023 RWCU E% V A RWCU-3-001-G024 RMCU E, P A RWCU-3-001-G025 RWCU P% V A RWCU-3-001-G026 RWCU T% V A RWCU-3-007-001 RWCU P$ -V A RWCU-3-007-002 RWCU P% V ~ A RWCU-3-007-003 RWCU P$ V A RWCU-3-007-004 RMCU P$ V A 1084(207)

0 1/3-81-4.6.G Page 88 APPENDIX A TABLE D-3A (Continued)

UNIT 3 WELDS RE UIRED TO BE EXAMINED PER GENERIC LETTER 88-01 WELD PIPE WELD IGSCC EXAM NUMBER SYSYEM SIZE'(INCHES CONFIG CATEGORY RCRD-3-49 CRD 4 E, V RCRD-3-50 CRD 4 E, V RCRD-3-52 CRD 4 P, V DCS-3-04 CS 12 P, P DCS-3-05 CS 12 P, V DCS-3-13 CS 12 P, P DCS-3-14 CS 12 P, V DSCS-3-01 CS 12 E, P DSCS-3-02 CS 12 E, P DSCS-3-07 CS 12 E, P DSCS-3-08 CS 12 E, E DSCS-3-09 CS 12 E, P TSCS-3-402 CS 10 P, SE TCS-3-405 CS 12 E, V TCS-3-406 CS 12 P, V TCS-3-410 CS 12 E, V TSCS-3-418 CS 10 P, SE TCS-3-421 CS 12 E, V TCS-3-422 CS 12 P, V TCS-3-426 CS 12 E, V GR-'3-01 RECIR 28 P, PMP GR-3-02 RECIR 28 P, V GR-3-04 RECIR 4 C, P GR-3-07 RECIR 4 C, P GR-3-28 RECIR 28 Ps V GR-3-29 RECIR 28 E, V GR-3-30 RECIR 4 C, P GR-3-33 RECIR 4 C, P GR-3-55 RECIR 28 P, T GR-3-56 RECIR 28 E, V GR-3-58 RECIR 28 ES PMP GR-3-61 RECIR 28 P, P GR-3-62 RECIR 28 E, V GR-3-63 RECIR 28 P, V GR-3-63A RECIR 4 F, F GR-3-63B RECIR 4 BC 1084(207)

0 1/3-SI-4.6.G Page 89 APPENDIX A TABLE D-3A (Continued)

UNIT 3 WELDS RE UIRED TO BE EXAMINED 'PER GENERIC LETTER 88-01 WELD PIPE SIZE WELD IGSCC EXAM NUMBER SYSTEM /INCHES) CONFIG CATEGORY KR-3-01 RECIR 4 BC KR-3-02 RECIR 28 E, P KR-3-04 RECIR 4 BC KR-3-23 RECIR 4 BC KR-3-24 RECIR 28 E, P KR-3-26 RECIR 4 BC KR-3-45 RECIR 28 E% P KR-3-46 RECIR 28 P, T KR-3-47 RECIR 28 E, P KR-3-48 RECIR 28 E, P KR-3-49 RECIR 4 BC KR-3-50 RECIR 28 E, P KR-3-51 RECIR 28 E, P KR-3-52 RECIR 28 E, P KR-3-53 RECIR 4 BC DRHR-3-02 RHR 24 P% V DRHR-3-04 RHR 24 E, P DRHR-3-05 'HR 24 P$ V, DRHR-3-06 RHR 24 P, V DRHR-3-07 RHR 24 P% V DRHR-3-'11 RHR 24 P$ V DRHR-3-13 RHR 24 E, P DRHR-3-14 RHR 24 E% V DRHR-3-15 RHR 24 P$ V DRHR-3-16 RHR 24 E, V DRHR-3-19 RHR 20 P, T DRHR-3-21 RHR 20 E% V DRHR-3-22 RHR 20 P$ V DRHR-3-23 RHR 20 P% V DSRHR-3-01 RHR 24 E, P DSRHR-3-02 RHR 24'4 E, P DSRHR-3-03 RHR P, P DSRHR-3-04 RHR 24 E, P DSRHR-3-04A RHR 24 E, P DSRHR-3-05 RHR 24 E, P DSRHR-3-05A RHR 24 E, P DSRHR-3-06 RHR 24 P% P DSRHR-3-07 RHR 24 E, P DSRHR-3-08 RHR 6 BC DSRHR-3-09 RHR 20 E, P DSRHR-3-10 RHR 20 E, P TRHR-3-191 RHR 20 E% V 1084(207)

1/3-SI-4.6.G Page 90 APPENDIX A TABLE D-3A (Continued)

UNIT 3 WELDS RE UIRED TO BE EXAMINED PER GENERIC LETTER 88-01 WELD PIPE SIZE WELD IGSCC EXAM NUMBER SYSTEM ~INCHES CONFIG CATEGORY N 1A-SE RPV 28 N$ SE N 1B-SE RPV 28 N% SE RCRD-3-33 RPV 4 C$ N TCS-3-401 RPV 10 N% SE TCS-3-417 RPV 10 Ni SE 3RWCU-09 RWCU 4 P% V DRHR-3-03 RHR 24 P$ V DRHR-3-12 RHR 24 P$ V GR-3-03(OL) RECIR 28 E, V GR-3-27(OL) RECIR 28 P% PMP GR-3-53(OL) RECIR 28 P% SE GR-3-54(OL) RECIR 28 Es P GR-3-57(OL) RECIR 28 P% V GR-3-59(OL) RECIR 28 P, SE GR-3-60(OL) RECIR 28 E, P t

GR-3-64(OL) RECIR 28 OL/E$ P DSRHR-3-11(OL) RHR 20 E, PMP DRHR-3-03B RHR 24 P, P DRHR-3-13B RHR 24 P, P 1084(207)

1/3-81-4.6.G Page 91 APPENDIX A TABLE D-3B UNIT 3 STAINLESS AND DISSIMILAR METAL FIELDS NOT SUBJECT TO GENERIC LETTER 88-01 EXAMS WELO PIPE SIZE WELD IGSCC EXAH ISI SHEET Sl5KE OCS-3-03 CS 12 P. V N/A . ISI-0331-C 01 TEMPERATURE EXCLUSION.

OCS-3-10 CS 12 E, V N/A ISI-0102-C 02 TEHPERATURE EXCLUSION.

OCS-3-11 CS 12 P, V N/A ISI-0102-C 02 TEMPERATURE EXCLUSION.

OCS-3-12 CS 12 P, V N/A ISI-0331-C 01 TEHPERATURE EXCLUSION.

OCS-3-14 CS 12 E, P N/A ISI-0102-C 02 TEHPERATURE EXCLUSION.

OSCS-3-16A CS 12 P. PEN N/A ISI-0331-C 01 TEHPERATURE EXCLUSION.

INACCESSIBLE IN PENETRATION X-16A.

OSCS-3-)6B CS 12 P, PEN N/A ISI-0331-C 01 TEHPERATURE EXCLUSION.

INACCESSIBLE IN PENETRATION X-16A.

12 E, V N/A ISI-0102-C 01 TEHPERATURE EXCLUSION.

TCS-3-206 CS 12 E, P N/A ISI-0102-C 01 TEHPERATURE EXCLUSION.

TCS-3-207 .CS 12 P. V N/A ISI-0102-C 01 TEHPERATURE EXCLUSION.

SHPCI-3-06 HPCI 12 F, P N/A CHH-2407-C 02 TEHPERATURE EXCLUSION.

SHPCI-3-07 HPC I 12 E, P N/A CHH-2407-C 02 TEHPERATURE EXCLUSION.

SHPCI-3-08 HPCI 12 E. P N/A CHH-2407-C 02 TEHPERATURE EXCLUSION.

SHPC I-3-09 HPCI 12 E, P N/A CHH-2407-C 02 TEHPERATURE EXCLUSION.

SHPCI-3-10 HPCI 12 E, F N/A CHH-2407-C 02 TEHPERATURE EXCLUSION.

1084(207)

1/3-SI-4.6.G Page 92 TABLE E BROHNS FERRY NUCLEAR PLANT CLASS 3 COMPONENTS UNIT 1 Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam

~Com onents ~Sam le ~Sam le ~of lns Month Month Month C~ate or Remarks A. RHRSH Supports 92(76*) 92 VT 92 92 92 IND-2600 IS I-0085-C B. EECH Supports 97(111*) 97 VT 97 97 98* IHD-2600 IS I-0086-C C. Fuel Pool Cooling Supports 64(72*) 64 VT 64 64 64 IHD-2600 ISI-0090-C UNIT 3 A. RHRSH Supports 145(102*) 145 VT 145 145 145 IND-2600 CHM-2416-C B. EECH Supports 148(122*) 148 VT 148 148 148 IND-2600 . CHM-2417-C C. FPC Supports 52(55*) 52 VT 52 52 52 IND-2600 CHM-2429-C

1/3-81-4.6.G Page 93 TABLE F CLASS 2 EXEMPTED COMPONENTS CORE SPRAY 47M813-1

1. Chemistry Exemption

a. From discharge of pumps A, B, C, and D to FCV 75-25, FCV 75-53, FCV 75-22, and FCV 75-50 (including pumps A, B, C, and D).

b. From suppression pool header to the suction of pumps A, B, C, and D and to HCV 75-12, HCV 75-40, and HCV 75-31.

2. Components which do not operate, other than ECCS, during normal reactor operation.

a. Pump test lines from FCV 75-50 and FCV 75-22 to the suppression pool.

RCIC (47W813-1

1. Chemistry Exemption

a. Pump discharge to FCV 71-40 (including pump).

b. Pump drive turbine 'discharge to suppression pool (including drive turbine).

2. Pressure and Temperature Exemption

a. Suppression pool suction from 16-inch core spray and 71-502 to pump suction.

HPCI (47M812-1)

1. Chemistry Exemption

a. Main pump discharge to FCV 73-35 and FCV 73-45 (including pump).

b. Booster pump discharge to main pump suction.

c. From FCV 73-3 and 73-586 to turbine inlet (including turbine).

d. From turbine outlet to suppression pool.

2; Pressure and Temperature Exemption

a. From suppression pool suction and 73-505 to booster pump suction.

END OF APPENDIX A 1084(207)'

1/3-SI-4.6.G Page 94 APPENDIX B LIST OF ASME SECTION XI BOUNDARY DRAWINGS AND ISI DRAWINGS 1084(207)

1/3-SI-4.6.G Page 95 BFN ASME SECTION KI BOUNDARY DRAWINGS UNITS 1 2 AND 3 (COLOR CODED-REPRODUCTIONS NOT AVAILABLE)

DRAWING NO. SXSTEN

l. 47W600-57A ISI ISI RCS Instrumentation 2~ 47W600-58A RCS Instrumentation

3. 47W600-135A Isl RCS Instrumentation

4. 47W610-43-1 ISI Condensate/RHR/RHRSW/RWCU/S&Wg Instrumentation

5. 47W610-43-4 ISI Main Steam/Feedwater/S&Wg Instrumentation

6. 47W1600-301 ISI RCS Instrumentation

7. 47W2600-302 ISI RCS Instrumentation

8. GE117C2556 ISI RCS Instrumentation

9. GE11702563 ISI RCS Instrumentation

10. GE117C2564 ISI RCS Instrumentation

11. GE164C5981 ISI RCS Instrumentation

12. GE164C5984 - ISI RCS Instrumentation

13. GE164C5985 ISI RCS Instrumentation NOTE: Since these are color coded drawings, reproductions are not available.

Controlled sets are available in most of the major organizations (NODS, NAINT, NE, gA, etc.) to be used by anyone with a need to determine Section XI boundaries.

1084(207)

,1/3-SI-4.6.G Page 96 BFN ASME SECTION XI BOUNDARY DRAWINGS UNITS 1 AND 3 (COLOR CODED-REPRODUCTIONS NOT AVAILABLE)

DRAWING NO. SYSTEM

1. 47W801-1 ISI Main Steam

2. 47W801-2 ISI Main Steam

3. 47W807-2 - ISI Turbine Drains and Miscellaneous Piping

4. 47W820-2 ISI CRD Hydraulic

5. 47W820-6 IS I CRD Hydraulic

6. 47W854-1 ISI Standby Liquid Control

7. 47W855-1 ISI Fuel Pool Cooling NOTE: Since these are color coded drawings, reproductions are not available.

Controlled sets are available in most of the major organizations (MODS, MAINT, NE, QA, etc.) to be used by anyone with a need to determine Section XI boundaries.

1084(207)

1/3-SI-4.6.G Page 97 BFN ASME SECTION XI BOUNDARY DRAWINGS UNIT 1 COLOR CODED-REPRODUCTIONS NOT AVAILABLE)

DRAWING NO. SYSTEM

1. 1-47E803-1 ISI Feedwater

2. 1-47E810-1 ISI RWCU

3. 1-47E811-1 ISI RHR

4. 1-47E812-1 ISI HPCI

5. 1-47E813-1 ISI RCIC

6. 1-47E814-1 ISI Core Spray

7. 1-47E817-1 ISI Nuclear Boiler

8. 1-47E822-1 ISI RBCCW

9. 1-47E844-2 ISI Raw Cooling Water

10. 1-47E852-1 ISI Floor and Dirty Radwaste Drain

11. 1-47E852-2 ISI Clean Radwaste and Decon Drain

12. 1-47E856-2 ISI Demineralized Water

13. 1-47E858-1 ISI RHRSW

14. 1-47E859-1 ISI EECW NOTE: Since these are color coded drawings, reproductions are not available.

Controlled sets are available in most of the major organizations (MODS, MAINT, NE, gA, etc.) to be used by anyone with a need to determine Section XI boundaries.

1084(207)

1/3-81-4.6.G Page 98 BFN ASME SECTION XI BOUNDARY DRAWINGS UNIT 3 (COLOR REPRODUCTIONS NOT AVAILABLE)

DRAWING NO. SYSTEM

1. 3-47E803-1 - 1SI Feedwater 2~ 3-47E810-1 ISI RWCU

3. 3-47E811-1 ISI RHR 4~ e-47E812-1 ISI HPCI 5~ 3-47E813-1 ISI RCIC

6. 3-47E814-1 ISI Core Spray

7. 3-47E817-1 ISI Nuclear Boiler

8. 3-47E822-1 ISI RBCCW

9. 3-47E844-2 ISI Raw Cooling Water

10. 3-47E852-1 ISI Floor and Dirty Radwaste Drain

11. 3-47E852-2 ISI Clean Radwaste and Decon Drain

12. 3-47E856-2 IS I Demineralized Water

13. 3-47E858-1 ISI RHRSW

14. 3-47E859-1 ISI EECW .

15. 3-47E859-2 ISI EECW

16. 3-47E866-5 ISI ' Air Conditioning Chilled Water

17. 3-47E866-7 ISI Air Conditioning Chilled Water Since these are color coded drawings, reproductions are not available.

Controlled sets are available in most of the major organizations (MODS, MAINT, NE, QA, etc.) to be used by anyone with a need to determine Section XI boundaries.

1084(207)

1/3-81-4.6'.G Page 99 LIST OF ISI DRAWINGS UNIT 1 TITLE Reactor Vessel CHM-0992-C Reactor Vessel Weld and Nozzle Locations CHM-2001-C Vessel Stud Locations CHM-2002-C Control Rod Drive Penetrations (Locations)

CHM-2102-A Closure Head Assembly MSG-0020-A Reactor Vessel Clad Patches Residual Heat Removal Heat Exchan ers CHM-2418-B RHR Heat Exchanger Welds Pi in S stem Weld Locations CHM-1080-C Feedwater System Code Class 1 CHM-1081-C Recirculation System Code Class 1 CHM-1082-C Main Steam System Code Class 1 CHM-1088-C Residual Heat Removal System Code Class 1 CHM-1089-C Core Spray System Code Class 1 CHM-1097-C CRD Hydraulic Return Line Code Class 1 CHM-1098-C Reactor Water Cleanup and RCIC Code Class 1 CHM-1099-C High Pressure'oolant Injection Code Class 1 ISI-0362-C RHR Shutdown Supply Code Class 2 CHM-2690-C Main Steam System Code Class 2 ISI-0029-C Closed Cooling Water System Code Class 2 ISI-0093-C RCIC Code Class 2 ISI-0091-C HPCI Code Class 2 ISI-0095-C Core Spray Code Class 2 ISI-0036-C CRD Header Code Class 2 ISI-0409-C Jet Pump Instrumentation Nozzle Class 1 ISI-0159-A Core Differential Pressure and Liquid Control Nozzle Class 1 ISI-0160-A Instrumentation Nozzles Class 1 MSG-0019-B Recirculation Inlet Nozzles Class 1 1084(207)

1/3-SI-4.6.G Page 100 LIST OF ISI DRAWINGS UNIT 1 (Continued)

DRAWING NO. TITLE Pi in S stem Su ort Locations CHM-2036-C Feedwater System Code Class 1 CHM-2037-C Recirculation System Code Class 1 CHM-2038-C Main Steam System Code Class 1 CHM-2039-C RHR System Code Class 1 CHM-2040-C Core Spray System Code Class 1 CHM-2042-C Reactor Water Cleanup and RCIC Code Cl'ass 1 CHM-2043-C High Pressure Coolant Injection Code Class 1 ISI-0363-C RHR Shutdown Supply Code Class 2 ISI-0030-C Closed Cooling Water Code Class 2 ISI-0049-C Main Steam System Code Class 2 ISI-0094-C RCIC Code Class 2 ISI-0092-C HPCI Code Class 2 ISI-0096-C Coze Spray Code Class 2 ISI-0037-C CRD Header Code Class 2 ISI-0085-C RHR Service Water Code Class 3 ISI-0391-C Raw Cooling Water Code Class 3 IS I-0090-C Fuel Pool Cooling Code Class 3 Pi e Boltin Main Steam Bolting Code Class 1 ISI-0022-B RHR Pump Support Code Class 2 Reactor Vessel Su ort ISI-0414-C Reactor Vessel Support Code Class 1 ISI-0420-C Recirculation Pump Bolting Code Class 1 1084(207)

1/3-SI-4.6.G Page 101 LIST OF ISI DRAWINGS UNIT 3 DRAWING NO. TITLE Reactor Vessel ISI-0267-C Vessel Stud Locations ISI-0293-C Control Rod Drive Penetrations (Locations)

ISI-0220-C Reactor Vessel Weld and Nozzle Locations ISI-0295-A Closure Head Assembly ISI-0317-A Reactor Vessel Clad Patches Residual Heat Removal Heat Exchan ers ISI-0422-C RHR Heat Exchanger Welds Pi in S stem Weld Locations ISI-0327-C Feedwater System Code Class 1 ISI-0328-C Recirculation System Code Class 1 ISI-0329-C Main Steam System Code Class 1 ISI-0330-C Residual Heat Removal System Code Class 1 ISI-0331-C Core Spray System Code Class 1 ISI-0332-C Reactor Water Cleanup, RCIC, and CRD Code Class 1 ISI-0333-C High Pressure Coolant Injection Code Class 1 ISI-0411-C Jet Pump Instrumentation Nozzle Code Class 1 ISI-0354-C . Main Steam Code Class 2 ISI-0393-C Residual Heat Removal System Code Class 2 ISI-0033-C Closed Cooling Water Code-Class 2 CHM-2408-C RCIC Code Class 2 CHM-2407-C HPCI Code Class 2 ISI-0102-C Core Spray Code Class 2 ISI-0143-C CRD Header Code Class 2 ISI-0344-A Core Differential Pressure and Liquid Control Nozzle Class 1 ISI-0346-A Instrumentation Nozzles Class 1 ISI-0348-B Recirculation Inlet Nozzles Class 1 1084(207)

1/3-SI-4.6.G Page 102 LIST OF ISI DRAWINGS UNIT 3 (Continued)

DRAWING NO. TITLE Pi in S stem Su ort Locations ISI-0334-C Reactor Water Cleanup and RCIC Code Class 1 ISI-0335-C High Pressure Coolant Injection Code Class 1 ISI-0336-C Feedwater System Code Class 1 ISI-0337-C Recirculation System Code Class 1 ISI-0338-C Ma'in Steam System Code Class 1 ISI-0339-C Core Spray System Code Class 1 ISI-0340-C RHR System Code Class 1 ISI-0395-C RHR System Code Class 2 ISI-0355-C Main Steam System Code Class 2 ISI-0034-C Closed Cooling Water Code Class 2 ISI-0104-C Core Spray Code Class 2 CHM-2413-C HPCI System Code Class 2 CHM-2412-C RCIC System Code Class 2 ISI-0144-C CRD Header Code Class 2 CHM-2416-C RHRSW Code Class 3 CHM-0390-C EECW Code Class 3 CHM-2429-C Fuel Pool Cooling System Code Class 3 Pi e Boltin Main Steam Bolting Code Class 1 ISI-0311-B RHR Pump Support Code Class 2 ISI-0413-C Recirculation Pump Bolting Code Class 1 Reactor Vessel Su ort ISI-0416-C Reactor Vessel Support Code Class 1 0 1084(207)

END OF APPENDIX B

1/3-SI-4.6.G Page 103 APPENDIX C CLASS 1 VALVE DATA 0 1084(207)

1/3-SI-4.6.G Page 104 Page C-2 APPENDIX C TABLE 1 CLASS 1 VALVE DATA CODE VALVE PIPING VALVE VALVE VALVE GROUP TVA Dwg. No. VENDOR HATERIAL VALVE FORGING/

GRIISi 3-554 AC Fdwtr. 24 I I Ck SA CHH-1080-C 20788-M Atwood& A-216 WCB PSIV Casting Horril1 3-558 AC Fdwtr. 24 l1 Ck SA CHH-1080-C 20788-H Atw&Hor A-216 WCB PSIV Casting 3-568 AC Fdwtr. 24 II Ck SA CHH-1080-C 20788-M Atw&Mor A-216 WCB PSIV Casting 3-572 AC Fdwtr. 24 II CL SA CHH-1080-C 20788-H Atw&Hor A-216 WCB PSIV Casting HCV 3-67 Fdwtr. 24" Gate Han CMM-1080-C 035879-2 Powell A-216 WCB Haint. Casting HCV 3-66 Fdwtr. 24 I I Gate Han CHH-1080-C 035879-2 Powell ~

A-216 WCB Haint. Casting FCV 68-1 Recirc 28 II Gate CMH-1081-C 94-12086 Darling A351 CFB Oper. Casting FCV 68-77 Recirc 28 I I Gate CHH-1081-C 94-12086 Darling A351 CFB Oper. Casting FCV 68-3 Recirc 28 II Gate HO CHH-1081-C 94-12086 Darling A351 CFB PSIV Casting FCV 68-79 Recirc 28" Gate HO CMH-1081-C 94-12086 Darling A351 CFB PSIV Casting FCV 68-33 Recirc 22 I I Gate CHH-1081-C 94-12086 Darl ing A351 CFB Oper. Casting FCV 68-35 Recirc 22w Gate CMH-1081-C 94-12086, Darling A351 CFB Oper. Casting FCV 1-14 H. Stm. 26 II Globe CO CMH-1082-C 20851-H Atw&Hor A216 WCB PSIV Casting FCV 1-26 H. Stm. 26ll Gl obe CO CHH-1082-C 20851-M Atw&Hor A216 WCB PSIV Casting FCV 1-37 H. Stm. 26ll Globe CO CMH-1082-C 20851-H Atw&Hor A216 WCB PSIV Casting FCV 1-51 H. Stm. 26" Globe CO CMH-1082-C 20851-H Atw&Hor A216 WCB PSIV Casting FCV 1-15 H. Stm. 26 I1 Globe CO CHH-1082-C 20851-H Atw&Mor A216 WCB PSIV Casting FCV 1-27 H. Stm. 26ll Globe CO CHH-1082-C 20851<<H Atw&Hor A216 WCB PSIV Casting FCV 1-38 H. Stm. 26n Globe CO CHH-1082-C 20851-H Atw&Hor A216 WCB PSIV Casting FCV 1-52 H. Stm. 26 II Globe CO CHH-1082-C 20851-H Atw&Hor A216 WCB PSIV Casting PCV 1-4 H. Stm. 6 II Rel SA ISI-0027-C PL-7657F-100 Trgt Rck See Note 1 HSRV Casting PCV 1-179 H. Stm. 6 II Rel SA ISI-0027-C PL-7657F-100 Trgt Rck HSRV Casting PCV 1-5 H. Stm. 6 II Rel SA ISI-0027-C PL-7657F-100 Trgt Rck HSRV Casting PCV 1-18 H. Stm. 6 II Rel SA ISI-0027-C PL-7657F-100 Trgt Rck HSRV Casting PCV 1-19 H. Stm. 6 II . Rel SA ISI-0027-C PL-7657F-100 Trgt Rck MSRV Casting PCV 1-22 M. Stm. 6 II Rel SA ISI-0027-C PL-7657F-100 Trgt Rck HSRV Casting PCV 1-23 H. Stm. 6 II Rel SA ISI-0027-C PL-7657F-100 Trgt Rck HSRV Casting PCV 1-30 H. Stm. 6 l1 Rel SA ISI-0027-C PL-7657F-100 Trgt Rck HSRV Casting PCV 1-31 H. Stm. 6 II Rel SA ISI-0027-C PL-7657F-100 Trgt Rck HSRV Casting PCV 1-34 H. Stm. 6 II Rel SA ISI-0027-C PL-7657F-100 Trgt Rck HSRV Casting PCV 1-41 H. Stm. 6 II Rel SA ISI-0027-C PL-7657F-100 Trgt Rck HSRV Casting PCV 1-180 H. Stm. 6 II Rel SA ISI-0027-C PL-7657F-100 Trgt Rck HSRV Casting PCV 1-42 H. Stm. 6 II Rel SA ISI-0027-C PL-7657F-100 Trgt Rck HSRV Casting MCV 74-69 RHR 24" Gate Han CHM-1088-C 035880-3 Powell A351 CFBH Haint. Casting HCV 74-55 RHR 24" Gate Han CHM-1088-C 035880-3 Powell A351 CFBH Maint. Casting 1084(207)

1/3-SI-4.6.G Page 105 Page C-3 APPENDIX C TABLE 1 (Continued)

CLASS ) VALVE DATA CODE VALVE PIPING VALVE VALVE VALVE GROUP TVA Dwg. No. VENDOR HATERIAL VALVE FORGING/

T P Q5XIHG FCV 74-68 1 AC RHR 24" Ck SA 9 CHH-1088-C 20800-H Atw&Hor A351 CFBH PSIV Casting FCV 74-54 1 AC RHR 24w Ck SA 9 CHH-1088-C 20800-H Atw&Hor A351 CFBH PSIV Casting FCV 74-67 1 A RHR 24" Gate NO 10 CHH-1088-C A-12334-H)E Walworth A351 CFBH PSIV Casting FCV 74-53 1 A RHR 24" Gate NO 10 CHH-1088-C A-12334-H1E Walworth A351 CFBH PSIV Casting HCV 74-49 1 RHR 20" Gate Han ll CHN-1088-C 036207-2 Powell A351 CFBN Maint. Casting FCV 74-47 1 A RHR 20" Gate NO 12 CHH-1088-C A-12332-H)C Walworth A216 WCB PSIV Casting 74-691 1 H Spray 6" Ck SA 13 CHH-1088-C P-33160-21 Velan A182 F316 Oper. Forging FCV 74-78 1 A H Spray 6n Gate HO 14 CHH-1088-C A-12323-H2G Walworth A351 CFBH PSIV Casting FCV 74-77 1 A H Spray 6" Gate MO 14 CMN-1088-C A-12323-M2G Walworth A351 CFBH PSIV Casting "85-577 1 CRD 4" Gate Han 15 CHH-1097-C P-339231-13 Vel an A)82 TP316 Haint. Forging HCV 75-55 'C Spray 12" Gate Han 16 CHH-1089-C 036034-2 Powell A351 CFBH Haint. Casting HCV 75-27 C Spray 12" Gate Han 16 CHH-1089-C 036034-2 Powell A351 CFBH Haint. Casting FCV 75-54 AC C Spray ')2" Ck SA 17 CHN-1089-C PD-420652 Rockwell A35) CFBH PSIV Casting FCV 75-26 1 AC . C Spray 12" Ck SA '17 CHN-1089-C PD-420652 Rockwell A351 CFBM PSIV Casting FCV 75-53 1 A C Spray 12" Gate HO 18 CHH-1089-C IVP-11978 Walworth A351 CFBH PSIV Casting FCV 75-25 1 A C Spray 12" Gate HO 18 CHH-1089-C IVP-11978 Walworth A351 CFBM PSIV Casting 69-500 1 RWCU 6" Gate Han 19 CHM-1098-C P-33160-20 Velan A)82 F316 Haint. Forging FCV 69-1"" 1 A RWCU 6" Gate HO 20 CHM-1098-C 435KAA-002 Borg- SA 105 pSIV Forging Warner FCV 69-1""" 1 A RWCU 6" Gate HO 21 CHH-2073-C P-33160-20 Velan A182 F316 PSIV Forging FCV 69-2 1 A RWCU 6" Gate NO 21 CHM-1098-C P-33160-20 Velan A182 F316 PSIV Forging

• 69-579 1 AC RWCU 4w CK SA 22 CHH-1098-C P-35177-4 Velan PSIV

%69-580 1 RWCU 4" Gate Man 23 CHM-1098-C P-35177-3 Vel an A105 GR)1 Haint. Forging FCV 71-40 1 A RCIC 6" Ck SA 24 CHN-1098-C PD-420688 Rockwell A216 WCB PSIV Casting h"69-628 1 RWCU 4" Ck SA 25 ISI-0333-C C-23650 Anchor SA-531 CFBH PSIV Casting Darling i&69-629 1 RWCU 4" Ck SA 25 ISI-0332-C C-23650 Anchor SA-531 CFBN PSIV Casting Dar)ing A"69-624 RWCU 4" Ck SA 26 IS I-0333-C P-33923-35 Vel an A182 F316 PSIV Forging

• Exempt from B-H-2 examination due to size.

""Unit 1

• "'Units 2 & 3 AUnit 3 only

1/3-SI-4.6.G Page 106 Page C-4 APPENDIX C TABLE 1 (Continued)

CLASS 1 VALVE DATA CODE VALVE PIPING VALVE VALVE VALVE GROUP TVA Dwg. No. VENDOR HATER IAL VALVE FORGING/

T N N FCV 73-2 1 A HPCI 10" Gate HO 25 CHH-1099-C PB-139989 Crane A216 WCB PSIV Casting FCV 73-3 1 A HPCI 10" Gate HO 25 CHH-1099-C PB-139989 Crane A216 WCB PSIV Casting FCV 73-45 1 A HPCI 14" Ck CO 26 CHH-1099-C PD-420687 Rockwell A216 'WCB PSIV Casting FCV 74-48 1 A RHR 20" Gate HO 27 CHH-1088-C A-12331-HlC Wal worth A351 CFBH PSIV Casting Note 1: HSRV's with serial numbers 1014, 1015, 1016, 1032, 1033, and 1034 are complete forgings (A105). All other HSRV's have cast bodies (A216 WCB) with forged top works (A105).

HO- Hotor Operated CO Cylinder Operated SA- Self-Actuating Han Hanual 1084(207)

.1/3-SI-4.6.G Page 107 APPENDIX C TABLE 2 System Valve Numbers (Flow Diagram Number)

Feedwa ter 96A (3-554)$ 28A {3-558)>> 29A {HCV 3-67), 96B (3-568), 28B (3-572)% 29B (HCV 3-66)

Recirculation 43A (FCV 68-1)% 53A (FCV 68-3)% 65A (FCV 68-35)% 65B (FCV 68-33), 53B (FCV 68-79), 43B (FCV 68-77)

Main Steam FCV 1-15, FCV 1-14$ PCV 1-5$ 1-501, PCV 1-4, FCV 1-27, FCV 1 26$ PCV 1 23$ PCV 1 22$ PCV 1 19 PCV 1 18 FCV' 38$ FCV 1-37, PCV 1-34, PCV 1-31, PCV 1-30, FCV 1-52, FCV 1-51, PCV 1-42% 1-537$ PCV 1-41 81A (HCV 74-69)% 46A (FCV 74-68)% 25A (FCV 74-67)% 81B (HCV 74-55), 46B (FCV 74-54)$ 25B (FCV 74-53), HCV 74-49% FCV 74-48, FCV 74-47 CRD Return 85-577, 85-576 Core Spray 14A (HCV 75-27), 13A {FCV 75-26), 12A (FCV 75-25), 14B {HCV 75-55)% 13B (FCV 75-54)% 12B (FCV 75-53)

RWCU 69-500, FCV 69-1, FCV 69-2,69-580, *69-628, *69-629, +69-624 RCIC FCV 71-40 HPCI FCV 73 2 $ FCV 73 3 $ FCV 73 45

• Unit 3 only END OF APPENDIX C 1084(207)

1/3-S1-4.6.G Page 108 APPENDIX D (This appendix intentionally deleted' 1084(207)

1/3-81-4.6.G Page 109 APPENDIX E (This appendix intentionally deleted) 0 1084(207)

1/3-SI-4.6.G Page 110 APPENDIX F DATA SHEETS 1084(207)

1/3-SI-4.6.G Page 111 APPENDIX F Data Sheet 1 BROWNS FERRY NUCLEAR PLANT UNIT , CYCLE INSERVICE INSPECTION FINAL REPORT Reviewed by:

Mechanical/Nuclear Engineering Representative Plant Manager 1084(207)

1/3-SI-4.6.G Page 112 APPENDIX F Data Sheet 2 Plant Manager Browns Ferry Nuclear Plant All in-service inspection work scheduled during the unit , cycle outage for the area designated below is complete. Also, all corrective actions specified in the Notification of Indication forms submitted during this outage are verified and the required reinspections are acceptable.

/ / Drywell / / Total Plant Mechanical/Nuclear Engineering Representative END OF APPENDIX F 1084(207)

1/3-SI-4.6.G Page 113 APPENDIX G REQUESTS FOR RELIEF 1084(207)

1/3-SI-4.6.G Page 114 RE UEST FOR RELIEF ISI-2

~tom onente: Reactor Pressure Vessel Class:

Function Pressure-retaining component.

Test Re uirement: Volumetric examination of reactor pressure vessel pressure-retaining welds, examination categories B-A and B-B.

Basis for Relief: The Browns Ferry Nuclear Plant was designed and under construction before the issuance of Section XI. As a result, only those welds above the sacrificial shield are accessible for inservice inspection. Access has not been provided in the sacrificial shield area for external examinations nor does the BWR design permit internal examinations in this area. Only those welds above the sacrificial shield and portions of welds as may be accessible at nozzle access points wil'1 be examined during the inservice inspection intervals.

Alternate Inspection: None.

1084 (207)

1/3-SI-4.6eG Page 115 REQUEST FOR RELIEF ISI-2 (SUPPLEMENT) e A. Welds that Cannot Be Examined Lower head bottom section to lower head center section circumferential seam weld (approximately 39 ft. long).* The lower head center section contains four longitudinal welds (approximately 2.5 ft. long each).* All other welds are identified on Drawing CHM-0992-C (unit 1)** and the inaccessible ones are listed below:

Weld Identification ~cate or C-S-BH (Circ. Seam approximately 54 ft. long) B-B V-BH-2 (Long. Seam approximately 6.5 ft. long) B-B V-BH-3 (Long. Seam approximately 6.5 ft. long) B-B V-BH-4 (Long. Seam approximately 6.5 ft. long) B-B V-BH-5 (Long. Seam approximately 6.5 ft. long) B-B V-BH-6 (Long. Seam approximately 6.5 ft. long) B-B V-BH-1 (Long. Seam approximately 6-5 ft. long) B-B C-BH-1 (Circ. Seam approximately 69 ft. long) B-B V-1-B (Long. Seam approximately 11 ft. 1 inch long) B-A V-1-A (Long. Seam approximately ll ft. 1 inch long) B-A V-1>>C (Long. Seam approximately 11 ft. inch long) 1 B-A C-1-2 (Circ. Seam approximately 69 ft. long) B-A 0 V-2-B (Long. Seam approximately 11 V-2-A {Long. Seam approximately 11 V-2-C (Long. Seam approximately 11 C-2-3 (Circ. Seam approximately 69 V-2-C (Long. Seam approximately ft. 1 inch long) ft. 1 inch long) ft. 1 inch long) ft. long) ll ft.

ft. 1 inch long)

B-A B-A B-A B-A B-B V-3-B (Long. Seam approximately 11 1 inch long) B-B B. Welds That Can Be Examined Weld Identification ~Cate or V-3-A (Approximately 4.5 ft. of 11 ft. l.inch Long.

Seam at nozzle opening) B-B C-3-4 (Approximately 27 ft. of 69 ft. Circ. Seam B-B accessible at nozzle opening)

V-4-B {Approximately 10 inches of 4' 0-3/8" Long.

Seam accessible above biological shield) B-B V-4-A (Approximately 10 inches of 4' 0-3/8" Long.

Seam accessible above biological shield) B-B V-4-C (Approximately 10 inches of 4' 0-3/8" Long.

Seam accessible above biological shield) B-B C-4-5 (Approximately 4.5 ft. of 69 Ft. Circ. Seam accessible by removable insulation) B-B V-5-A (Total Long. Seam 11 ft. 1 inch accessible by B-B removable insulation) 1084(207)

1/3-SI-4.6.G Page 116 0 V-5-C REQUEST FOR RELIEF (Total Long. Seam ll ft.

ISI-2 1

(SUPPLEMENT) inch accessible by (Cont'd)

B-B removable insulation)

V-5-B (Total Long. Seam 11 ft. 1 inch accessible by B-B removable insulation)

C. ~Summar Accessible Length Code Required Meld Code Required weld Not Required By Code Cate or Len th Accessible Len th Inaccessible Code B-A NONE 6.6 ft. Long. Seam NONE 6.6 ft. Circ. Seam B-B 5.9 ft. Long. Seam 7.1 ft. Long. Seam 31.9 ft. Long. Seam 7.0 ft. Circ. Seam 8.1 ft. Circ. Seam 24.5 ft. Circ. Seam

• Category B-B

• • CHM-2046-C (Unit 2) and ISI-0220-C (Unit 3) details same weld numbers.

1084(207)

1/3-SI-4.6.G Page 117 RE UEST FOR RELIEF ISI-3

~Cam onants: Reactor Pressure Vessel Support Skirt Class:

Function Support component.

Test Re uirement: Volumetric examination of support attachment weld to vessel, examination category B-H.

Basis for Relief: Approximately 6 feet of the attachment weld would require examination to meet code requirements.

However, nonremovable reactor vessel insulation limits inservice examination. Two access ports, approximately 180 degrees apart, provide access for examination of two 2-foot lengths. Four feet of the support skirt-to-reactor vessel weld will be ultrasonically examined during each inspection interval.

Alternate Inspection: None.

0 1084(207)

1/3-SI-4.6eG Page 118 RE UEST FOR RELIEF ISI-4 REVISION 1

~corn onente: Reactor Recirculation Pumps Class:

Function Provides a variable reactor power rate by varying core coolant flowrate.

Test Re uirement: Visual examination of pump internal pressure boundary surfaces, examination category B-L-2.

Basis for Relief: During maintenance, if required, visual examination of the recirculati.on pump internal pressure boundary surface is performed and documented under existing plant procedures.

In the absence of required maintenance, as is the case with the recirculation pumps at Browns Ferry during the first 10-year interval, disassembly of a recirculation pump solely to perform a visual examination of internal surfaces is impractical. This would represent unnecessary exposure of employees to high radiation and contamination areas and excessive expense to TVA.

Disassembly of this pump could require transport of the motor outside of containment; consequently, a possibility of damage to the pump, pump motor, or other safety-related equipment exists. Time required for this major task of disassembly, examination, and reassembly would 'consume at least three weeks of 24-hours-per-day work. Radiation dose rates of the pump exterior will average 10-20 rem/hour. This would result in a cumulative dose of between 100 and 300 man-rem.

The benefit received from this major effort is minimal considering employees exposure, potential damage to safety-related equipment, and cost. Relief from the visual examination B-L-2 requirement is, therefore, requested.

Alternate Inspection: A. None planned. As long as the flows, pressure and temperatures are as specified in the Byron-Jackson recirculation pump manual, no disassembly for routine visual examination is recommended.

B. Conduct the required Code visual inspection of the interior during the cycle 6 outage.

1084(207)

1/3-SI-4.6.G Page 119 RE/VEST FOR RELIEF ISI-4 (Cont'd)

Alternate Monitoring: A. Install monitoring instrumentation on each pump for pump shaft vibration caused by mechanical fatigue-driven crack growth with appropriate control room instrumentation.

B. Install monitoring instrumentation for contamination of component cooling water (COW) by reactor coolant water caused by crack growth in the pump covers to the extent that a leak path develops between the two systems with appropriate control room instrumentation.

1084 (207)

1/3-SI-4.6.G Page 120 RE UEST FOR RELIEF ISI-5 REVISION 1 C~om onents: Valves exceeding 4-inch pipe size Class:

Function Various Test Re uirement: Visual examination of internal pressure boundary surfaces, examination category B-M-2.

Basis for Relief: During routine maintenance, visual examinations of valve body internal pressure boundary surfaces are performed and documented under existing plant administrative procedures. If no valve within a group has been disassembled for maintenance as the end of the interval approaches, relief from the visual examination B-M-2 requirements is requested. The attachments hereto present the valve groups requiring visual examination and the specific groups for each Browns Ferry Nuclear Plant unit for which relief is requested.

Alternate Inspection: If no valves from a particular group have been disassembled as the end of the interval approaches, the valves comprising that group shall be visually examined for leakage when the system pressure tests (IWA-5000) are conducted in accordance with the requirements for Category B-P.

1084(207)

.1/3-SI-4.6.G Page .121 TABLE 1 REQUEST FOR RELIEF ISI-5 Valve Grou s Re uirin .Internal Pressure Boundar Visual Examination B-M-2)

Check 24" Atwood & Morrill 3-554, 3-558, 3-568, 3-572 FW Gate 24" Powell HCV3-66, HCV3-67 Recirc. Gate 28" Darling FCV68-1$ FCV68-77 Recirc. Gate 28" Darling FCV68-3, FCV68-79 Recirc. Gate 22" Darling FCV68-33, FCV68-35 MS Globe 26" Atwood & Morrill FCV1-14% FCV1-15%

FCV1-26$ FCV1-27$

FCV1-37% FCV1-38$

FCV1-51, FCV-52 MS Relief 6" Target Rock PCV1-4% PCV1-5$

PCV1-18, PCV1-19%

PCV1-22, PCV1-23, PCVl-30$ PCV1-31, PCV1-34, PCV1-41, PCVI-42%

PCV1-179, PCV1-180 8 RHR Gate 24" Powell HCV74-69% HCV74-55 9 RHR Check 24 Atwood & Morrill FCV74-54, FCV74-68 10 RHR Gate 24" Walworth FCV74-53, FCV74-67 11 RHR Gate 2Pt> Powell HCV74-49 12 RHR Gate 20" Walworth FCV74-47 13 RHR Check 6$ $ Velan 74-691 14 RHR Gate 6 II Walworth FCV74-77$ FCV74-78 16 CS Gate 12" Powell HCV75-27$ HCV75-55 17 CS Check ] 2%I Rockwell FCV75 26$ FCV75 54 18 CS Gate ] 2$ $

Walworth FCV75-25, FCV75-53 19 RWCU Gate 6%1 Velan 69-500 20* RWCU Gate 6 II Borg-Warner* FCV69-1*

21 RWCU Gate 6$ $ Velan FCV69-1**, FCV69-2 24 RCIC Check 6" Rockwell FCV71-40 25 HPCI Gate 10" Crane FFCV73-2% FCV73-3 26 HPCI Check 14" Rockwell FCV73-45 27 RHR Gate 20$ $ Walworth FCV74-48

• Unit 1 only

• • Units 2 & 3 1084(207)

l/9-SI-4.6.G Page 3.22 TABLE 2 REQUEST FOR RELIEF ISI-5 Unit 1 Valve Grou s Not 0 ened for Maintenance Grou Number(s) Function Basis For Relief Later Later Later 1084(207)

1/3-SI-4.6.G "

Page 123 0 TABLE 2 REQUEST FOR RELIEF ISI-5 Unit 2 Valve Grou s Not 0 ened for Maintenance Grou Number s Function Basis For Relief Maintenance Block valve to vessel; fuel must be removed and ~essel drained.

Operation Requires fuel removal and vessel drained. Bonnets have been seal welded to prevent leakage.

Pressure safety Requires fuel removal and vessel isolation drained. Bonnets have been seal welded to prevent leakage.

Operation Requires fuel removal and vessel drained. Bonnets have been seal welded to prevent leakage.

Maintenance Requires fuel removal and vessel drained.

Maintenance Requires fuel removal, vessel drained, and both RHR loops out<<of-service.

12 Pressure safety Requires fuel removal, vessel isolation drained, and both RHR loops out-of-service.

16 Maintenance Requires fuel removal and vessel drained.

18 Pressure safety Requires leak rate testing.

isolation 19 Maintenance Requires fuel removal and vessel drained.

21 Pressure safety Requires leak rate testing.

isolation 27 Pressure safety Requires leak rate testing.

isolation Requires both RHR loops to be out-of-service.

1084(207)

'I 1/3-SI-4.6.G Page 124 TABLE 4 REQUEST FOR RELIEF ISI-5 Unit 3 Valve Grou s Not 0 ened for Maintenance Grou Number s) Function Basis For Relief Later Later Later 1084 (207)

1/3-SI-4.6.G Page 125 RE VEST FOR RELIEF ISI-6

~Com onents: Control Rod Drive Housing Welds Class:

Function Pressure-retaining component.

Test Re uirement: Uolumetric examination of peripheral CRD housing welds, examination category B-O.

Basis for Relief: Should the CRD housing weld fail, the leakage path to the failure meets the make-up exclusion criteria and is therefore excluded from volumetric examination in accordance with IWB-1220(b)(1). The make-up supply system is equivalent to 4-inch nominal pipe size. The smallest leakage path area would be realized between the guide cap and thermal sleeve as shown on the

~

attached diagrams. The following calculations verify exclusion of volumetric examination in accordance with IWB-1220(b)(1):

For 3-inch nominal pipe size (maximum code exclusion):

D = 3.068 inches, A = (]){D /4), where A = internal transverse area D = inside diameter A3 in = 7.39 in. 2

~

For the thermal sleeve:

DTS = 4.25 inches ATS = 14.19 in.

~

2 For the guide cap:

DGC = 4.125 inches, AGC = 13.26 in.

~

2 Total leakage path area:

ALP = ATS AGC = 14.19 in. -13.36 in. = 0.83 in.

A3 in ~ = 7 '9 in ~

2 ALp = 0.83 in.

Therefore, ALP ( A3 in Alternate Inspection: All peripheral CRD housing welds .shall be visually examined during the system hydrostatic pressure tests in accordance with IWB-1220(c).

1084(207)

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1/3-SI-4.6.G Page 127 RE UEST FOR RELIEF ISI-7

~Gom onents: Inaccessible welds in piping penetrations and under rigid pipe restraints Class:

Function Pressure-retaining component.

Test Re uirement: Volumetric examination of pressure-retaining welds in piping, examination category B-J.

Basis for Relief: The penetration flued head to process pipe welds are inaccessible for any type of examination. The penetrations involved are feedwater, two per unit 24" O.D., main steam four per unit 26" O.D., RHR four per unit 2-24" O.D., 1-20" O.D., 1-6" O.D., core spray two per unit 12" O.D., RWCU one per unit 6", O.D., and HPCI one per unit 10" O.D. Four main steam welds and two feedwater welds on each unit are located under rigid pipe restraints and are inaccessible for volumetric examination. The welds located under the rigid pipe restraints are identified in the inservice inspection program. There are also six feedwater welds on unit 3 located under pipe supports (KFW-3-40, KFW-3-41, KFW-3-42, KFW-3-43, KFW-3-44., and KFW-3-45).

Alternate Inspection: A "Best Effort" visual examination will be performed during

\

the system hydrostatic pressure test.

1084(207)

1/3-81-4.6.G Page 128 RE UEST FOR RELIEF ISI-8 REVISION 2

~Com onents: Pressure-Retaining fields in Piping Class: 1 and 2 Function Pressure-retaining component.

Test Re uirement: Volumetric examination of longitud-inal, circumferential, pipe branch connection and valve body welds, examination categories B<<J, B-F, C-F, and B-M-1.

Basis for Relief: In some cases it will be impractical to inspect all welds in accordance with paragraph T-532 of Article 5,Section V, of the ASME Code, i.e.,

nonremovable hanger interference or valve and pump casings adjoining the welds. These welds will be noted on the ultrasonic examination data sheets.

In addition to the visual examination performed during system leakage and hydrostatic pressure tests, a "best effort" ultrasonic examination will be performed. Also, a surface examination will be performed on accessible areas of the weld(s).

~Re ortin The tables attached hereto provide a listing of the welds which are covered by this request for relief. Units 1 and 3 welds will be added as t'e end of the first 10-year interval for those units approaches.

1084(207)

1/3-SI-4.6.G Page 129

. TABLE 1 REQUEST FOR RELIEF ISI-8 h

UNIT 1 WELDS RE UIRING ALTERNATE SURFACE EXAMINATION WHEN ACCESSIBLE WELD IDENTIFICATION SCAN LIMITATION REASON Later Later Later 1084(207)

1/3-SI-4.6.G Page 130 TABLE 2 REQUEST FOR RELIEF ISI-8 UNIT 2 MELDS RE UIRING ALTERNATE SURFACE EXAMINATION WHEN ACCESSIBLE Meld Identification Scan Limitation Reason TCCW-2-1 (8") 3/No Scan;4/5:30-7:00 3/Penetration; 4/Meld-0-Let TCCW-2-5 (8") 3/No Scan;3/6:30-7:30 4/Penetration; 3/2" pipe attachment DCS-2-3 (12") 3 & 4/No Scan 3/Valve Geometry 4/Penetration DCS-2-12 (12") 3 & 4/No Scan 3/Valve Geometry; 4/Penetration TCS-2-406 (12") 4/No Scan'/2:00 4/Valve Geometry; 3/Welded Brace TCS-2-421 (12") 3/No Scan; 4/8:30-9:00 3/Valve Geometry; 4/Instrument Line 3/No Scan; 4/5:00-7:00 3/Valve Geometry; 4/Inner Radius RCRDS-2-2 (6") 3 & 4/No Scan 3 & 4/Tee &

Reducer Geometry KFW-2-26 (24") 3,4,5, &6/12: 00 3-6/1" Pipe Attachment KFM-2-28 (20") 3,4,5,&6/12:00 3-6/1" Pipe Attachment N4A-SE (12") All scans limited All/Safe-End

.Configuration N4B-SE (12") 3,415,&6/8:00 & 9:00 3-6/ 3/4" Diameter Welded Pads

'4D-SE (12") 4/No Scan; all/12:00-3:00, 4/Configuration; 4:00-6:00 All/ Sensor Line Attachments N4E-SE'12") 4/No Scan; All/8:00-9:00, 4/Configuration; 12:00-3:00$ 4:00-6:00 All/ Sensor Line Attachments 1084(207)

1/3-SI-4.6.G Page 131 TABLE 2 (Continued)

REQUEST FOR RELIEF ISI-8 UNIT 2 WELDS RE UIRING ALTERNATE SURFACE EXAMINATION WHEN ACCESSIBLE Weld Identification Scan Limitation Reason N4F-SE (12") All Scans limited All/Safe-End Configuration THPCI-2-72 (10") 3/No Scan; 4/5 00-7:00 3/Valve Geometry; 4/Brace .

GMS-2-2 (26") 3/No Scan; 4/ 1/2 node 3/Valve penetration 4/Penetration GMS-2-2-LS (26") 7,8,9,&10/2" through 12" 7-10/ Penetration GMS-2-10-LS (26") 7,8,9,&10/4" through 12" 7-10/ Penetration KMS-2-25-LS1 11,12,13,&14/No Scans 11-14/Covered by 8 6:00 (26") I-beam 11,12,13,&14/8" through 12" 11-14/Non-Removable Insulation DRWC-2-1A (6") 3 & 4/No Scan 3/Reducer Geometry; 4/Valve Geometry DRWC-2-2 {6") 4/No Scan 3/11:30-12 30 4/Valve Geometry; 3/1" Weld-0-Let DRWC-2-3 (6") 3/No Scan; 4/10:00-11:00, 3/Valve Geometry; 5:30-6:30 4/Vent Pipe &

Instrument Line GR-2-3-LS2 11,12,13,&14/No Scans 11-14/Support Lug 9 12:00 '(28")

GR-2-8 '(28") 3 & 4/No Scan 3 & 4/Cross to Tee

& Tee Geometry GR-2-34 (28") 3 & 4/No Scan 3 & 4/Cross to Tee

& Tee Geometry GR-2-56 (28") 4/No Scan; 3,5,&6/ 4/Configuration; ll:45 to 12:30 & 10:30 3-6/Weld Attachment 1084{207)

1/3-SI-4.6.G Page 132 TABLE 2 (Continued)

REQUEST FOR RELIEF ISI-8 UNIT 2 WELDS RE UIRING AITERNATE SURFACE EKAMINATION WHEN ACCESSIBLE Weld Identification Scan Limitation Reason GR-2-63A (4") No Scans Seal Welded Blind Flange KR-2-51-LS (28") 7,8,9,&10/6" through 12" 7-10/Rigid Restraint DRHR-2-3 (24") 3 & 4/No Scan 3/Valve Geometry; 4/Penetration DRHR-2-3-LS (24") 7,8,9,&10/4" through 12" 7-10/Penetration DRHR-2-5 (24") 4/No Scan 3/ll:00-1:00 4/Valve Geometry; 3/Support Attachment DRHR-2-12 (24") 3 & 4/No Scan 3/Valve Geometry; 4/Penetration 3,4,5,&6/6:00 3-6/Non-Removable Support TRHR-2-262 (20") 3 & 4/11:00-1:00 & 3:00 3 & 4/Hanger Mounting Bracket &

Catwalk Support TRHR-2-462 (6") ~ 3,4,5,&6/5:00-7:00 3-6/Welded Support 1084(207)

1/3-SI-4.6.G Page 133 TABLE 3 REQUEST FOR RELIEF ISI-8 UNIT 3 WELDS RE UIRING ALTERNATE SURFACE EXAMINATION WHEN ACCESSIBLE Weld Identification Scan Limitation Reason Later Later Later 1084 (207)

1/3-SI-4.6.G Page 134

'RE UEST FOR RELIEF ISI-9

~Com onente: Integrally-Welded External Support Attachments for Piping and Valves Class:

Function Support components.

Test Re uirement: Volumetric examination of the support attachment welds, examination categories B-K-1.

Basis for Relief: During the first Browns Ferry baseline inspection, the ultrasonic examinations of the integrally-welded Class 1 supports were meaningless because of the lack of penetration indications that existed for the full length of the support welds. The supports were fabricated to ANSI B31.1.0 and General Electric Company specification 21A2100. The GE specification required a full penetration weld and surface examination requirements, which would not verify penetration. The TVA Division of Engineering Design has taken actual weld dimensions of randomly-chosen piping supports and compared the load capabilities of these welds as installed to the loads based on design the supports would see during operation. As indicated in the attached analysis, all supports studied have high factors of safety in their load-carrying capability; therefore, we feel the integrally-welded supports on the primary coolant piping are acceptable as installed. Further ultrasonic examinations of these supports would. be meaningless.

Alternate Inspection: Class 1 integrally-welded supports will be liquid penetrant examined in place of ultrasonic examinations. The liquid penetrant examinations performed during each inspection interval will cover 25 percent of the integrally-welded supports.

10S4(207)

1/3-SI-4.6.G Page 135 PIPE SUPPORTS-PRIMARY COOLANT PIPING COMPARISON OF DESIGN LOADS AND WELDS TO "AS-BUILT" Pipe Design Load Ca abilit of Factor of Support Load Meld As Veld As Safety No. Desi ed Installed As Installed CSR-8 1,000 lb

• 39,188 lb 44,467 lb 44.5 CSR-9 2,000 lb

• 39,188 lb 51,034 lb 25.5 CSR-1 1,000 lb

• 39,188 lb 44,467 lb 44.5 CSR-2 2,000 lb

• 39,188 lb 51,034 lb 25.5 RHR-69 4,200 Ib *110,000 lb 115,200 Ib 24.4 RHR-68 8,400 lb 76,776 lb 9.2 RHR-67 8%000 lb

• 98,129 lb 117,755 lb 14.7 SSA1,2,5, 6( 6 1%250 lb 57%600 lb 46.1 SSA8 (X) 12,993 lb

• 87,000 lb 57%600 lb 4.4 SSA9 (Z)

SSA7 (Z) 4,375 lb

• 72,194 lb 86,400 lb 19.7 SSB7 (Z) ssc4 (z) 17%750 lb

• 72,194 lb 57%600 lb 3.2 ssB4 (z) 15,000 lb

• 72,194 lb 57,600 lb 3.8 SSB6 (X) 19,900 lb

• lb 72,000 lb 3.6 SSB5 (Y) 13%800 lb lb 57%600 lb 4.2 Sscl (Z) 27%500 lb

• lb 126,000 lb 4.6 SSB2 (X 30 600 lb

• lb 151 200 lb 5.0 BLANKS INDICATE INSUFFICIENT INFORMATION AVAILABLE 1084(207)

1/3-SI-4.6.G Page 136

• The "Designed" weld would equal or exceed the strength of the 'attachment if it were a full penetration bevel weld as shown. The load capacity shown is the tensile or shear strength of the attachment.

NOTE: The load capacities of the "as installed" welds are based on an allowable shear strength of 14,500 psi, or 600 lb per 16th of an inch of leg per linear inch of weld for fillet welds.

1084(207)

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I/3-S1-4.6.G Page 137 ADDITIONAL INFORMATION REGARDING INSERVICE INSPECTION PROGRAM REQUEST FOR RELIEF ISI-9 BROWNS FERRY NUCLEAR PLANT UNIT 3 (DOCKET NO. 50-296)

To provide justification for Request for'Relief ISI-9 an analysis was performed on a selection of integral supports that are subject to fatigue loading. Integral welds in the latest sample indicated substantially higher stress allowable factors of safety with a minimum factor of 8.3 calculated.

Attached is a list of assumptions used in the analysis and a summary of analysis results. Based on these results, we believe that the integral support welds are entirely acceptable, and relief from the inservice volumetric examination requirements of the ASME Section XI Code is justified.

1084(207)

,1/3-SI-4.6.G Page 138

1. Due to lack of full penetration, fillet welds were assumed with a base dimension equal to the specified penetration grove opening.

2. Restraint loads as specified by the support assembly drawings were applied.

3. Effective area of the fillet welds was in accordance with paragraph XVII-2452.5, Appendix XVII, Section III, ASME Code.

4. 'hear and tensile stresses in the welds were combined by the maximum shear stress formula to compare with the fillet weld shear allowables presented in paragraph NF-3291.)-l, Subsection NF,Section III, ASME Code. The minimum specified shear allowable is applied in all cases.

5. No stress concentration factors were applied. The high factors of safety moxe than offset any concentration effects.

SUMMARY

OF RESULTS PIPE INTEGRAL ATTACHMENT WELDS HANGER LOAD POUNDS) MAXIMUM SHEAR STRESS SAFETY FACTOR RHR-R-74 840 463 PSI 39 1 RHR-H-1*

RHR-H-3*

MS-H-B1, -Cl*

MS-H-B2, -C2*

RWC-H-1+

15940 11075 3606 6350 1300 2155 1367 740 1425 854 PSI PSI PSI PSI PSI 8.3 13.2 24.3 12.6 21.0 HPCI-H-1 (H152) 6060 1630 PSI 11.0 HPCI-H-2 (H48) 2368 1070 PSI 16.8 RH-2, 12* 11800 1780 PSI 10'. 1 RH-1, -9* 13400 1719 PSI 10. 5 RH-10, -11* 8900 1342 PSI 13.4

• For these lugs, drawings call out full penetration plus fillet welds.

1084(207)

1/3-SI-4.6.G Page 139 RE UEST FOR RELIEF ISI-10

~Com onents: Ultrasonic Calibration Standards Class: 1 and 2 Function Ultrasonic calibration for examination of welded components.

Test, Re uirement: Ultrasonic calibration blocks fabricated to 1974 Edition, Summer 1975 Addenda, of Section XI, IWA-2232.

Basis for Relief: Ultrasonic calibration blocks employed for the Browns Ferry baseline examination were fabricated to the 1971 Edition of Section XI. These blocks will continue to be used for future examinations to ensure the repeatability of data. The pipe blocks have 5XT sawtooth notches running circumferentialy around the inside and outside diameters. One side-drilled hole is placed in the side of the block parallel to the longitudinal axis of the curved blocks. Pipe block curvature is within 0.9 to 1.5 times the diameter of the pipe examined; and thickness and hole size are according to ASME Section III, Figure lX-3432.'1 of the 1971 Edition, Summer 1971 Addenda. Material for all blocks was the same or equivalent "P" number except as discussed in the attached file note and shown in the mill test report also attached.

Alternate Inspection: Future examinations which require .fabrication of new calibration blocks will be performed using calibration blocks which will meet the 1974 Edition, Summer 1975 Addenda of Section XI, except for piping blocks which will as a minimum meet the 1977 Edition, Summer 1978 Addenda of ASME Section XI.

1084(207)

1/3-S1-4.6.G Page 140 FILE NOTE DETERMINATION OF ACOUSTIC PROPERTIES OF VARIOUS CALIBRATION BLOCKS FOR USE IN INSERVICE INSPECTIONS AT BROWNS FERRY NUCLEAR PLANT.

During recent metallurgical examinations of calibration blocks used for baseline and inservice inspections at Browns Ferry, it was shown that four calibration blocks were not made from material of the same or equivalent P'number as the material that was examined. Since this same or equivalent P number is required by Appendix IX of Section III of the ASME Boiler and Pressure Vessel Code, it was necessary to determine the acoustic properties of these four blocks with respect to material of the components.

Calibration blocks BF 11Cy BF 12Cy BF 13'nd Automation Industries AISI 4340 3-inch area amplitude block S.N. 1219 were used to examine materials of different P number. The velocity and attenuations in these blocks were compared to the material they were used to examine as described in the following paragraphs.

Block,BF-llC was made'rom A515 grade 70 material while block BF-12C was made from A515 grade 55 material. Both blocks were used to calibrate for A533 grade B material. To demonstrate similarity, both blocks were compared to BF-10C, which is A533 grade B, for sound velocity and attenuation.

Using a Krautkramer type USIP-1CW ultrasonic flow detector, with an Automation Industries 2.25 MHz, type SFB 3/8-inch effective diameter crystal, these back reflections from the 3.007-inch side of BF-12C were placed at the 3-, 6-, and 9-inch locations on the CRT graticule. The crystal was then placed on the 3.992-inch of BF-11C. Back reflections were observed at the 4- and 8-inch locations on the CRT graticule. After this, the crystal was placed on the 4.032-inch side of BF-10C. The first back reflections occurred between 4.000 and 4.050 inches and was interpreted to be 4.025 inches. The second back reflection occurred between 8.000 and 8.100 inches and was interpreted to be 8.050 inches.

By the above process, it was determined that the velocity of sound was essentially the same through all three blocks.

To check attenuation an Automation Industries 5 MHz, type SFB, 3/8-inch effective diameter crystal was placed on the 4-inch thickness of BF-10C.

With the first back reflection set at 60 percent of full scale, the gain setting read 42 dB. The gain was then increased to 51 dB to bring the second back reflection up to 60 percent scale height. This gave an attenuation of 0.75 dB/inch. This procedure was repeated on the 4-inch side of BF-11C with a change in dB from 58 to 42. This gave an attenuation of 2.5 dB/inch. The 2.2-inch side of BF-12C was then evaluated and a change in dB from 36 to 45 was necessary to bring the second back reflection up to 60 percent full scale. This gave an 1084{207)

'1/3-SI-4.6.G Page 141 attenuation of 1.5 dB/inch. All three measurements were reported three times with the same results. It can be seen that calibration with BF-llC or BF-12C would give a more sensitive examination than is required.

BF-13, which is A437 grade B4C, is used to calibrate for A540 grade B23 material. Using an Automation Industries 5-MHz, type SFB, 3/8-inch effective diameter crystal, the 100-inch scale of the ultrasonic instrument was checked for linerity using an Automation Industries'ISI 4340 3-inch block S.N. 1219 and a 65.6-inch reactor closure head stud made from A540 grade B23 material. When the crystal was placed on the 69-inch BF-13, a back reflection was seen within 1 inch of the desired reading, which is as close as the scale can be resolved on the 100-inch scale. To check for attenuation, the back reflection of BF-13 was set at 80 percent scale height with a gain setting of 43 dB. The same amplitude was obtained on the reactor closure head stud using 42 dB. On the basis of the above tests, BF-13 is considered a satisfactory calibration block for A540 grade B23 material.

The Automation Industries'ISI 4340 3-inch area amplitude block S.N.

1219 is also used for examining recirculation pump nuts made from A194 Cl. 24 material. Both nut and block were 3 inches thick. Both distances measured 3 inches by using the USIP-1CW Krautkramer ultrasonic flow detector with an Automation Industries 5 MH, type SFB, 3/8-inch effective diameter crystal. Attenuation was checked on the nut by setting the first back reflection to 50 percent of full scale and then bringing the second back reflection up to 60 percent by using the gain control. A total of 12 dB was required to do this, giving a material attenuation of 2 dB/inch. This was repeated for the calibration block with identical results. These two materials are therefore considered similar with respect to velocity and attenuation.

1084(207)

u 1/3-SI-4.6.G Page 142 DETERMINATION OF ACOUSTIC PROPERTIES OF VARIOUS CALIBRATION BLOCKS FOR USE IN INSERVICE INSPECTION AT BROWNS FERRY NUCLEAR PLANT

~Summur Calibration Block No. Material Attenuation BF-10C A533, Grade B 0.75 dB/inch BF-11C A515, Grade 70 2.50 dB/inch BF-12C A515, Grade 55 1.50 dB/inch Attenuation is less in BF-10C than in either BF-11C or BF-12C.

Therefoxe, use of BF-12 to calibrate a scope for use in testing A533, grade B, material will result in a test more sensitive than required and is acceptable.

Block BF-13 was found to have the same attenuation as the 65.5-inch studs for which it was used as a calibration block.

Block Automation Industries AISI 4340 was formed to have the same attenuation as the nuts for which it was used as a calibration block.

0 There were no variations or discrepancies in any of the velocity or propagation tests.

Descri tion of the Blocks:

BF-10C A533, Grade B Supplied by Magnaflux Used for flange-to-vessel welds Attenuation - 0.75 dB/inch BF-11C A515, Grade 70 Used for nozzle-to-head, head, and nozzle-to-vessel welds Supplied by SKI after unit 1 inspection Attenuation 2.25 dB/inch BF-12C A515, Grade 55 Used for support skirt welds Attenuation 1.5 dB/inch BF-13 Crucible 422 Used for 65.5-inch studs Attenuation same as studs 1084(207)

1/3-SI-4.6.G Page 143 Descri tion of the Blocks:

Automation Industries AISI 4340, 3-inch area amplitude block S.N. 1219 Contains 1/8-inch flat bottom hole 3 inches from top surface Total length of block approximately 3-3/4 inches.

Used for nuts Attenuation identical to the nuts The procedure for determining attenuation is given in Krautkramer ultrasonic test instructions.

1084(207)

/

1/3-SI-4.6.G Page 144 COMBUSTION ENGINEERING, INC. (CE)

TVA-BRONNS FERRY ULTRASONIC CALIBRATION BLOCKS TVA CE Identif. Identif. P Si Ni Cr Mo Comments BF-1C P-14607 0.204 0.96 0.03 0.016 0.21 <0.010 <0.01 <0.01 0.001 A106, GR.B BF-2S P-14608 0.035 0.47 0.019 0.012 0.41 9.940 18.67 0.06 0.030 A358, 304 SS BF-3C P-14609 0.250 0.93 0.019 0.021 0.14 <0.010 <0.01 <0.01 <0.001 A106, GR. B BF-4S P-14610 0.048 1.66 0.032 0.016 0.41 9.600 18.54 0.2 0.040 A358, 304 SS BF-5C P-14611 0.250 0.85 0.003 0.022 0.17 0.030 0.01 <0.01 <0.001 A106, GR. B BF-6S P-14612 0.053 1.60 0.021 0.018 0.52 10.470 10.37 0.17 0.050 A358, 304 SS BF-7C P-14613 0.260 0.0 0.004 0.020 0.13 <0.010 <0.01 <0.01 <0.001 A105, GR. 8 BF-BS P-14614 0.035 1.60 0.020 0.009 0.53 0.510 10.17 0.10 0.040 A240, 304 SS BF-9C P-14615 0.230 0.62 0.007 0.017 0.02 0.010 <0.01 <0.01 <0.001 A36 (A283)

BF-10C P-14616 0.230 1.22 0.010 0.015 0.22 0.470 0.09 0.49 <0.003 A533. GR. 8 BF-11C P-14617 0.330 0.74 0.008 0.023 0.21 0.070 0.02 <0.01 <0.001 A515, GR. 70 BF-12C P-14618 0.220 0.65 0.011 0.024 0.20 0.040 <0.01 <0.01 <0.001 A515, GR. 55 BF-13 P-14619 0.250 0.87 0.020 0.014 0.33 0.750 11.19 0.93 0.250 A437, BR. 84C P-14620 0.210 0.44 0.013 0.020 0.11 0.020 <0.01 <0.01 <0.001 A519, GR. MT 1020 BF-15C 1084(207)

1/3-SI-4.6.G Page 145 tern: RE VEST FOR RELIEF ISI-11

~Ss Main steam Class:

Test Re uirement: Surface examination of support members for piping examination category C-E-1.

Basis for Relief: The main steam system includes four special restraints, each of which is partly embedded in a wall. Each embedded restraint includes 12 guide lugs which are welded to the process pipe. These welds are inaccessible for examination. Each restraint also includes 12 stop plates welded to the process pipe which are accessible for examination. They shall be surface examined during the inspection interval (see attached drawings).

Alternate Inspection: None.

0 1084 (207 )

MAIN STEAM PlPj:NG

~ 0

~ ~

SPECIAL RESTRAINTS SEE DETAIL "A rosa(2o7)

0 EXAMINE EXTERNAL INTEGRAL ATTACHMENTS IN THESE AREAS ONLY II Bll I CII "C"

00 4P 0 I CO t M c- i

'4 C SECTION "C" - "C" SECTION "B" "B" 0 A

I J

1/3-SI-4.6.G Page 148 RE UEST FOR RELIEF ISI-12 C~om onents: Pressure retaining longitudinal welds in piping Class:

Function: Pressure retaining component Test Re uirement: Volumetric examination of pressure-retaining longitudinal welds in piping, examination category B-J.

Basis for Relief: See the attached supplement for weld identification, estimated extent of code examination, and reason for limitation.

Alternate Inspection: A surface examination will be performed on the accessible code required length of the weld.

1084(207)

1/3-SI-4.6.G Page 149 REQUEST FOR RELIEF ISI-12 (SUPPLEMENT)

UNIT 3 Long Seam Adjacent to Weld Percent Ins ection Limitation GR-3-62 Prohibited by support lug KR-3-51 50 Scan limited to 6" by support DCS-3-4 25 Scan limited to 5" by support DCS-3-5 65 Scan limited to 8" by support DCS-3-13 50 Scan limited to 6" by penetration GMS-3-2 16 Scan limited to 2" by penetration GMS-3-3 50 Scan limited to 6" by support GMS-3-9 50 Scan limited to 6" by penetration GMS-3-10 15 Scan limited to 2" by penetration GMS-3-11 50 Scan limited to 6" by penetration GMS-3-15 15 Partial scan limited by insulation ring GMS-3-32 15 Partial scan limited by insulation ring GMS-3-18 50 Scan limited to 6" by penetration GMS-3-19 25 Scan limited to 3" by penetration GMS-3-20 15 Scan limited to 6" by penetration GMS-3-27 50 Scan limited to 6" by penetration 10,84 (207)

1/3-SI-4.6.G Page 150 REQUEST FOR RELIEF ISI-12 (SUPPLEMENT)

UNIT 3 Long Seam Adjacent to Weld Percent Ins ection Limitation GMS-3-28 15 Scan limited to 2" by penetration GMS-3-29 50 Scan limited to 6" by penetration DSRHR-3-9 35 Scan limited to 4" by support DSRHR-3-7 35 Scan limited to 4" by support DSRHR-3-6 35 Scan limited to 4" by support DSRHR-3-5A 10 Scan limited to 1" by elbow radius DSCS-3-4 Scan limited by elbow curvature DRHR-3-13 50 Scan limited to 6" by penetration KMS-3-105 75 Partial scan limited by support lug 1084(207)

1/3-SI-4.6.G Page 151 RE VEST FOR RELIEF ISI-13

~Com onents: RHR Heat Exchangers units 1, 2, and 3 Class:

Function: Pressure retaining nozzle welds in vessels Test Re uirement: Volumetric examination of nozzle-to-vessel attachment welds, examination category C-B.

Basis for Relief: The RHR heat exchangers nozzle-to-vessel attachment weld is covered by a reinforcement ring (shown in the attached sketch) which does not allow access to any of the attachment weld.

Alternate Inspection: The reinforcement ring welds are accessible and will be given a surface examination. Two reinforcement rings on each unit will be examined over the 40-year inspection interval in accordance with IWC-2411 on ASME Section XI.

1084(207) 4 h

RIIR I IEA 7 EXCHANGER hfDZZLE REINIFORCEMEhlT RING NOZZLE l.O.

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R H 518 MC SHELL X.O.

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1/3-SI-4.6.G Page 153 e RE VEST FOR RELIEF ISI-14

~Com onente: Pressure-retaining bolting Class:

Ins ection Re uirements: Visual, surface, and volumetric examination of pressure-retaining bolting exceeding one inch in diameter, examination category C-D.

Basis for Relief:, Examination of class 2 pressure-retaining bolting in accordance with the Summer 1975 Addenda of Section XI exceeds inspection requirements for class 1 pressure-retaining bolting. We do not feel an increased level of. safety is obtained from a more restrictive examination of class 2 components. An examination program for class 2 pressure-retaining bolting similar to that for class 1 would be desirable. This type of examination has been incorporated in later additions of the code which Browns Ferry will be required to meet in the future.

Alternate Inspection: Class 2 pressure-retaining bolting exceeding two inches in diameter shall be volumetrically examined in accordance with Table IWC-2500-1, examination category C-D of the 1977 Edition, Summer 1979 Addenda of Section ZI. Pressure-retaining bolting two inches or less in diameter will not be examined.

1084 (207)

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~ C, 1/3-S 1-4.6. G Page 154 RE VEST FOR RELIEF ISI-15 Comron nts: Ultrasonic examination technique of piping welds.

Class: 1 and 2 f Function: Ultrasonic calibration piping components.

and examination of welded Test Re uirement: Appendix III III-3410 Material.

III-3430 Calibration Notches.

III-4450 Inaccessibility Welds.

Basis for Relief: The ultrasonic examination (IWA-2232(b),

IWA-2232(c), and Appendix III) and evaluation (IWA-3000) of piping welds is being updated to the 1977 Edition, Summer 1978 Addenda of ASME Section XI to provide state-of-the-art methods for both. There are existing requests fo" relief (addressed to the 1974 Edition of the ASME Code) from the test requirements listed above. We do not believe the existing requests for relief (ISI-8 and ISI-10) affect the overall purpose of updating the examination and evaluation techniques.

Ve request relief to remain to the 1974 Edition, Summer 1975 Addenda and the existing requests for relief for calibration block material, calibration notches, and inaccessible welds.

Alternate Inspection: As specified in ISI-8 and ISI-10.

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