ML18025B687
| ML18025B687 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/29/1981 |
| From: | Bymem J TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18025B688 | List: |
| References | |
| SI-4.6.G, NUDOCS 8111240787 | |
| Download: ML18025B687 (474) | |
Text
ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS PERRY NUCLEAR PLANT SURVEILLANCE INSTRUCTION 4.6. G INSERVICE INSPECTION PROGRAM UNITS 1, 2, and 3 APPROVED:
o Plant Sup intendent SEP S9 ~981 8111240787 8111 ib i PDR ADOCK 05000259 rilL44I.IFIF'lit'l@k ii LllilQIIlll:.'l II"hi.lI.'lIII $
8 PDR
I SFI'23 IS81 TABLE OF CONTENTS
- 1. 0 STATEMENT OF APPLICABILITY 2.0 PURPOSE 3.0 INSPECTION INTERVALS AND INSPECTION CYCLES 4.0 CODES OF RECORD 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 12.0 QUALIFICATIONS OF NONDESTRUCTIVE EXAMINATION PERSONNEL 13.0 ACCEPTANCE CRITERIA 14.0 REPAIRS AND REPLACEMENTS 15.0 RECORDS AND REPORTS 16.0 NOTIFICATION OF INDICATION 17.0 CALIBRATION BLOCKS 18.0 REQUESTS FOR RELIEF 19.0 AUGMENTED INSPECTIONS
20.0 REFERENCES
- APPENDIX A - Tables and Drawi'ngs
+APPENDIX B - Tables of Inservice Examinations
+APPENDIX C - Calibration Block Drawings
+APPENDIX D - Notification of Indication
+APPENDIX E - Augmented-Inspections
+APPENDIX F - Data Sheets
+APPENDIX G
'- Requests for Relief
0 BFNP SI"4.6.G SEP 29 1983 1.0 STATEMENT OF APPLICABILITY This program outlines details. for planning and performing the first 10-year inservice nondestructive examinations of Browns Ferry Nuclear Plant ASME Code Class 1, 2 and 3 components. The program is organized to fulfill inservice inspection requirements of the Browns Ferry Operational Quality Assurance Manual, Part II, Section 5.1, and comply as practical with the requirem nts of Section XI of the ASME Boiler and Pressure Vessel Code. In addition, this program implements applicable portions of the Browns Ferry Technical Specifications (4.6.G). In accordance with 10 CFR Part 50, 50.55a(g), this program meets the inservice inspection requirements to the extent practical.
Specifics concerning performance of nondestructive examinations are not a part of this program but are included in nondestructive examination procedures (DPM NSOE3).
2.0 PURPOSE The Inservice Inspection Program (ISI) is employed to obtain dat'a which can be used to determine or of a generic nature, which if would a component flaw is individual signal for examination of like components in the system.
Personnel responsible for performance of the examinatioqs should familiarize themselves with the requirements of this program prior to performing the examinations.
The examinations required by this program will 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-art nondestructive testing. .The ISI program will also detail components to be examined, examination methods selected, components examined during previous outages, and schedule charts foi planning examinations.
3.0 INSPECTION INTERVALS AND INSPECTION CYCLES The inservice examinations required by ASME Section XI shall be performed during each ten-year interval of service (inspection interval). The inspection intervals represent calendar years after the unit has been placed into commercial service. The first ten-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 six months or more, the inspection interval may be extended for an equivalent period.,
'0 BFNP SI"4.6.G Page 2 b~r 2. i8S1 The inspection interval shall be separated into three inspection cycles (40-month, 80-month, and 120-month).
Except for examinations that may be deferred to the end of the inspection interval, the required examinations shall be performed in. accordance with the following schedule.
Minimum Examinations Maximum Examinations Ins ection C cle Com leted Com leted 40-month 25 3 -1/3 80-month 50 66-2/3 120-month 100 . 100 The examinations deferred to the end of the inspection interval shall be completed by the end of the inspection interval.
K This program incorporates units 1, 2, and 3 into a concurrent cycle (letter to NRC LOO 801231 705) beginning July. 1, 1980. By extending the inspection interval one year (IWA-2400), the 80-month inspection cycle will begin July 1, 1981.
Appendix B lists the examinations performed on each unit during the first 40-month cycle.
4.0 CODES OF RECORD This program was prepared to meet the requirements of the 1974 Edition, Summer 1975 Addenda of Section XI of ASME Boiler and Pressure Vessel Code. Repairs and replacements will be in accordance with 1977 Edition, Summer 1978 Addenda of ASME Section XI (IWA-4000 and IWA-7000 respectively). Ultrasonic examination technique of piping welds will be in accordance with Appendix III of the 1977 Edition, Summer 1978 Addenda of ASME Section XI (Request for Relief ISI-15). Ultrasonic evaluation of piping welds will be in accordance with 1977 Edition, Summer 1978 Addenda of ASME Section XI. (The first 40<<month inspection cycle requirements for units 1 and 2 were in accordance with the 1971 Edition, Summer 1971 Addenda, of ASME Section XI.)
5.0 METHOD OF IMPLEMENTATION AND RESPONSIBILITIES Weld maps, component drawings, and tables are included in Appendix A to define ar'eas subject to examination (in additi.on to sections 7.0, 8.0, and 9.0).
The NCO QA Staff shall prepare scan plans for each inservice inspection using component drawings in this program for systems or components requiring examinations. The plans should include, as a minimum, references to components to be examined, methods of examination, examination procedures, and calibration standards.
Prior to performing examinations on a system or component", the
'scan plans shall be established and submitted to the plant superintendent for information.
letter from L. M. Mills to T. A.:Ipyolito date~ecember. 24,M9&0
BFNP SI-4.6.G Page 3 SEP 23 1981 When inservice examinations are implemented by instructions other than this program (i.e., MMI's), copies of the instruction data sheets shall be submitted to the NCO QA Staff by the performing organization such that these examinations may be included in the reports discussed in Section 15.0. These additional imple-menting instructions are referenced in sections 7.1.3, 7.1.5, 7.1.8, 7.5.1, 7.5.2," and 7.6.2 of this program.
If variations in piping configuration are discover'ed or replacements or repairs are made during the course of the ISI, these changes shall be marked on field copies of drawings. This information shall be communicated to the Metallurgy and Standards Group, which shall be responsible for revising the drawings and incorporating the revised drawings in this program. NCO QA Staff scan plan shall also be revised to reflect these changes. All latest revision scan plan information and other pertinent information shall be incorporated in this program when each inservice examination required by this program has been completed.
The inservice examinations will be performed by either QA Staff personnel or outside contractors. Contract preparation, adminis-tration, and supervision will be the responsibility of the NCO QA Staff. Inspection plans and/or Quality Assurance programs submitted by outside contractors shall be reviewed and approved by the NCO QA Staff prior to use. All specific NDE procedures used during the inspection program shall be reviewed and approved in accordance with OQAM Part II, Section 6.3.
Whenever inspection requirements are being accomplished under the jurisdiction of NUC PR, a NCO QA Staff representative shall be responsible to coordinate activities or obtain inspection data.
He will be the designated TVA representative to ensure contract compliance and to ensure proper disposition of needed procedure changes to both TVA and/or contractor procedures in accordance with approved vendor QA program and Section 6.3, Part II of the OQAM.
Additionally, the NCO QA Staff representative will,be responsible for notifying the Plant Superintendent of all unacceptable indications as soon as practical. Whenever an unacceptable indication is discovered, the procedure and form in Appendix D shall be utilized. In those cases where an outside contractor is furnishing inservice examination services, it will be the responsi-b l. lity of the contractor to initiate the form in Appendix D under the supervision of the NCO QA Staff representative. See section 16.
6 0 of this program.
When inservice examinations are completed, Data Sheet 1 in Appendix F of this program shall be completed and used as a cover sheet. for the final report (section 15.0) sent to the plant. The Plant Superintendent shall approve the final report by signing Data Sheet l.
BFNP SI-4.6.G SEI S~ 198'I ISX program preparation is the responsibility of the Metallurgy and Standards Group of the Controls and Test Branch. Any revisions initiated by other groups shall be submitted to the Metallurgy and Standards Group for informal approval prior to incorporating the revisions into this program.
6.0 ABBREVIATIONS AND DEFINITIONS 6.1 AIA - Authorized Inspection Agency.
6a2 AI - Authorized Inspector (may denote an ANI or ANII).
6e3 ANI - Authorized Nuclear Inspector.
6.4 ANXI - Authorized Nuclear Inservice Inspector.
6a5 ~tom 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. ~fns ection - Denotes verifying the performance of examinations and tests by an Inspector representing an Authorized Inspection Agency.
6a8 Maintenance - Routine servicing or work on a component
. undertaken to correct or prevent an unsatisfactory condition.
Maintenance does not include welding, heat treating, or defect removal which affects the pressure boundary. Mainte-nance includes operations such as lapping of valve seats, adjustment of stem packing, and pump seal maintenance.
Maintenance does not require the presence of or verification by the Authorized Inspector.
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.
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"s'atirfactor~peraMn'g condition.
BFNP SI-4.6.G s(F23 1981 component. It also includes the addition of components such as valves, and system changes such as 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 will be examined for the first ten-year 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).
Examinations performed during any one inspection that reveal indi-cations exceeding allowable standards of Article IWB-3000, in a component of an examination category shall be extended to include an additional number (or areas) of components within the same category, approximately equal to the number (or areas) initially examined during the inspection.
In the event further indications in excess of the allowable standards are revealed, all of the remaining number (or areas) of the components shall be examined to the extent specified in Table IWB-2500 for the inspe'ction interval.
Table A of Appendix A supplies additional information such as distribution of examinations during inspection cycles, reference drawing numbers, and ASME Section XI, Table 1WB-2500, Examination Categories.
T.l Reactor Vessel 7,1.1 Reactor Vessel Seam Welds Certain welds listed in this section are not accessible due to sacrificial shielding. No alternate inspection is proposed (see Request for Relief ISI-2). Sketches CHM-1095-A, sheets 1-5, show typical cross sections of the various welds to be examined.
BPNP SI"4.6.G SEP 291991 7.1.1.1 Lon itudinal and Circumferential Seam Welds in Core Re ion There are two circumferential and six longitudinal seam welds in this region.
All seam welds in the core region are inaccessible for inservice inspection.
The shell course is a cylindrical weldment fabricated of manganese-molybdenum steel (chemistry in RPV manual), and is clad internally with weld deposited austentic stainless steel.
7.1.1.2 Lower Head Seam Welds There are ten longitudinal seam welds circumferential seam welds in this and'wo region. All the seam welds in the lower head region are inaccessible for inservice inspection 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 nine longitudinal welds outside the core region (totaling 78 feet), seven of which have a total of approximately 41 feet of weld accessible for inservice inspection. Ten percent of each longitud-
.inal .weld is required to be examined during the inspection interval. A total of 5.9 feet, 1.1 feet of four welds (V-5-A, V-5-B, V-5-C, and V-3-A) and 0.5 feet of three welds (V-4-A, V-4-B, and V-4>>C),
shall be ultrasonically examined.
There are three circumferential welds in this region (totaling 207 feet), two of which have approximately 79 feet of weld accessible for inservice inspection.
Five percent of each circumferential weld is required to be ultrasonically examined during the 'inspection-interval ~he examinations shall be performed on at least 3-1/2 feet of each weld (C>>3-4 and C-4-5).
BFNP Sl"4.6.0 Page 7 SEP 29 1981 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.
7.1.1.4 Closure Head Seam Welds There are six meridional welds, totaling 48 feet. Ten percent of each weld (0.8 feet) is required to be examined during the inspection interval. To simplify the examination, one foot of each of the six welds (RCH-1"IV, -2V, -3V,
<<4V, -5V, and -6V) shall be ultrasonically examined. There is one circumferential weld (RCH-l-lC), totaling 38 feet. Five 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 is 69 feet in length and is accessible for inservice inspection. The entire length of the weld shall be examined during the inspection interval. The inservice inspection of this weld will be performed by ultrasonic techniques from the flange seal and bolting surface only.
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 is 66 feet long and is accessible for inservice inspection.
The entire length of the weld shall be examined during the inspection interval.
BFNP SI-4.6.G Page 8 SEP 89 1981 The flange forging is ASTM A-508 CL.2 steel conforming to ASME Code Case 1332"2.
It is not clad.
Reactor Vessel Nozzles All nozzles greater than three inch nominal pipe size will be examined during the first, ten-year 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. I 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 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.
Sketches CHM-1094-A, sheets 1"3 and 5-7, show the typical weld cross sections. Table A of Appendix A outlines the size of each nozzle and scheduled inspections.
Reactor Vessel Studs Nuts Washers Bushin s and Flan e Li aments The examinations shall cover 100 percent 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.
, BFNP SI-4.6.G Page 9 SEP 2'0 'l98l In addition, the closure studs shall be ultrasonically and magnetic particle examined when removed from 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 MHI-1, 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 ASIDE Code Case 1335"2, Paragraph 4, Class 3.
Reactor Vessel Pressure Retainin Boltin Two Inches and Smaller in Diameter There is no pressure retaining bolting two inches or smaller in diameter.
Control Rod Drives and Penetrations The CRD housing welds are exempted from volumetric examination by meeting the makeup exclusion criteria of IWB-1220 (b) (1) of ASME Section XI (see Request for Relief ISI-6). All 40 peripheral CRD housing shall be visually examined during system 'elds pressure tests to meet the alternate inspection.
There are 55 flux monitor penetrations, one level control nozzle penetration, and one drain nozzle penetration in the lower head. There are six instrumentatioh nozzle penetrations in the vessel shell. At least 25 percent of each group of penetrations of comparable size and function will be visually inspected for signs of leakage during system pressure test according to IWA-5240, ASME Section XI.
System. pressure tests of the penetrations is included in Surveillance Instruction 3.0.
BFNP SI-4.6.G Page 10 SEC 29 1981 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 (30O and 210 ). The four feet of weld shall be ultrasonically examined during the inspection interval (see Request for Relief ISI-3). Sketch CHM-10'91-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.
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 will'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.
7.1.8 Reactor Vessel Interior The space above. and below the vessel core that is made accepsible by the removal of components during normal refueliag 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. This examination may be performed at or near the end of the inspection interval.
BFNP SI-4.6.G Page ll SEP 29 1981 The general surveillance of the reactor vessel internals is in accordance with MMI 14.3-A.
7.2 Pi in Pressure Bounds The ultrasonic examinations for the inspection interval shall include 100 percent of the area of approximately 25 percent of the Class 1 circumferential veld joints, 3 inches and larger, 100 percent of the Class 1 dissimilar metal veld joints, 3 inches and larger, and one foot of the adjoining sections of longitudinal weld joints'lso approximately 25 percent of the branch connections larger than six inches in diameter shall be ultrasonically examined.
Surface examinations shall include approximately 25 percent of the branch connections six inches in diameter and smaller.
Several welds are inaccessible for inservice inspection.
Four RHR welds are located in containment, penetrations.
Four mainsteam and tvo feedwater welds are located under rigid supports. These welds will be given a "best effort" visual examination during system pressure tests (see Request for Relief 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 will receive a "best effort" ultrasonic examination and '
surface examination of accessible areas of the weld.
These welds will be noted as requiring. the additional surface examination on the ultrasonic examination data sheet (see Request for Relief ISI-8).
Several longitudinal welds are partially inaccessible for examination. No alternate examination is proposed (see Request for Relief ISI-12).
r 7.2.1 Recirculation Pi in There are 88 (Units 1, 2, and 3) Class 1 circumfer-ential pressure retaining pipe welds (including 12 pipe-to<<vessel nozzle safe end welds) and 15 (Units 1, 2, and 3) Class 1 branch connection pressure retaining pipe welds in the recirculation piping system subject to examination. The entire system is stainless steel, and all the 12-inch and larger piping has longitudinal veld seams. A total of 22 circumferen-tial welds (approximately 25 percent) and 4 branch connection welds (approximately 25 percent) shall be examined during the inspection interval. See Table A of Appendix A for weld size and scheduled inspections.
BFNP SI-4.6.G Page 12 S~P 29 1981 Main Steam Pi in There are 104 (Unit 1), 101 (Unit 2), and 102 (Unit 3) Class 1 circumferential pressure retaining pipe welds (including 4 pipe-to-vessel nozzle safe end welds), 27 (Units 1, 2, and 3) Class 1 branch connection pressure retaining pipe welds, and 6 (Unit 1, 2, and 3) pipe whip protection welds in the main steam piping subject to examination.
There are also four welds under piping supports that are inaccessible on each unit (KMS-l, KMS-81, KMS-29, and KMS-56). The entire system is carbon steel and all 26 inch piping has longitudinal weld seams. A total of 27 (Unit 1) and 26 (Unit 2 and 3) circumferential welds (approximately 25 percent),
8 (Units 1, 2, and 3) branch connection welds (approximately 25 percent), and 6 (Units 1, 2, and
- 3) pipe whip restraint welds (100 percent) shall be examined during the inspection interval. See Table A of Appendix A for weld size and scheduled inspections. The pipe whip protection welds are also scheduled in Table A and are listed individually in Table C of Appendix A.
Feedwater Pi in There are 57 (Units 1 and 2), and 63 (Unit, 3)
Class 1 circumferential pressure retaining welds (including 6 pipe-to-vessel nozzle safe end welds), 2 (Units 1, 2, and 3) Class 1 branch connection pressure retaining welds, and 10 (Units 1, 2, and 3) pipe whip protection welds in the feedwater piping system subject to examination. There are also two welds under piping supports that are inaccessible on each unit (KFW-4, KFW-22). .The entire system is carbon steel. A total of 15 (Units 1 and 2) and 16 (Unit 3) circum-ferential welds (approximately 25 percent), 1 (Units 1, 2, and 3) branch connection weld (approximately 25 percent), and 10 (Units 1, 2, and 3) pipe whip restraint welds (100 percent) shall be examined during the inspection interval. See Table A of Appendix A for weld size and scheduled inspections.
The pipe whip protection welds are also scheduled in Table A and are listed individually in Table C of Appendix A.
BFNP SI-4.6.G Page 13 SLP S> 198<
Core S ra Pi in There'are 27 (Unit 1), 18 (Unit 2), and 19 (Unit 3)
Class 1 circumferential pressure retaining welds (including 2 pipe-to-vessel nozzle safe end welds),
4 (Units 1, 2, and 3) pipe whip protection welds, and 8 (Units 2 and 3) dissimilar metal welds in the core spray system subject'o examination. There are also two welds inside each penetration that are inaccessible on Unit 1 (DSC-1-12A and DSC-1-4A)..
The Unit 1 system is stainless steel and the Units 2 and 3 systems have been changed to carbon steel, from the stainless steel safe end to valves FCV 75-54 and FCV 75-26 (the valves are stainless steel). A total of 7 (Unit 1) and 5 (Units 2 and 3) circumferential welds (approximately 25 percent),
4 (Units 1, 2, and 3) pipe whip restraint welds (100 percent), and 8 (Units 2 and 3) dissimilar metal welds (100 percent) shall be examined during the inspection interval. See Table A of Appendix A for weld size and scheduled inspections. The pipe whip protection welds are also scheduled in Table A and are listed individually in Table C of Appendix A.
Residual Heat Removal Pi in There are 61 (Unit 1), and 58 (Unit 2 and 3)
Class 1 circumferential pressure retaining welds, 1 (Units 1, 2, and 3) Class 1 branch connection pressure retaining weld, 3 (Units 1, 2, and 3) pipe whip protection welds, and 2 (Units 1, 2, and 3) dissimilar metal welds in the RHR system subject to examination. There are also five welds inside different penetrations that are inaccessible on the units (TRHR-1-192, TRHR-2-193, TRHR-3-193, .
DRHR-1-3B, and DRHR-1-13B). The majority of the system is stainless steel. The 20-inch and 6-inch piping through the penetrations is carbon steel.
A total of 16 (Unit 1), and 15 (Units 2 and 3) circumferential welds (approximately 25 percent),
1 (Units I, 2, and 3) branch connection weld percent), 3 (Units 1, 2, and 3) pipe whip '100 protection welds (100 percent), and 2 (Units 1, 2,
~
and 3) dissimilar metal welds (100 percent) shall be examined during the inspection interval. See Table A of Appendix A for weld size and scheduled inspections.
The pipe whip protection welds are also scheduled in Table A and are listed individually in Table C of Appendix,A;
BFNP SI-4.6.G Page 14 SEP 29 1981 Control Rod Drive H draulic Return Pi in There are 10 (Units 1, 2, and 3) Class 1 circumfer-ential pressure retaining welds (including the nozzle cap weld) and 1 (Units 1, 2, and 3) dissimilar metal weld in the control rod drive hydraulic return system subject to examination. The system is carbon steel except for a dissimilar metal weld to the valve (85-77). A total of 3 (Units 1, 2, and 3) Class 1 circumferential welds (approximately 25 percent) and 1 (Units 1, 2, and 3) dissimilar metal welds (100 percent) shall be examined during the inspection interval. See Table A of Appendix A for weld size and scheduled inspections. t Reactor Water Cleanu Pi in There are 19 (Unit 1), 16 (Unit 2), and 18 (Unit 3)
Class 1 circumferential pressure retaining welds and 4 (Units 1, 2, and 3) pipe whip protection welds in the reactor water cleanup system subject to examination.
The system is divided into a stainless steel section and a carbon steel section. A total of 5 (Units 1, 2, and 3) Class 1 circumferential welds (approximately 25 percent) and 4 (Units 1, 2, and 3) pipe whip protection welds (100 percent) shall be examined during the inspection interval. See Table A of Appendix A for weld size and scheduled inspections.
The pipe whip protection welds are also scheduled in Table A and are listed individually in Table C of Appendix A.
Reactor Core Isolation Coolin Pi in There are 4 (Units 1 and 3) and 6 (Unit 2) Class 1 circumferential pressure boundary pipe joint welds reactor c'are isolation cooling system subject to in'he examination. The system is carbon steel. A total of 1 weld (per unit) will be examined during the inspection interval. See Table A of Appendix A for weld size and scheduled inspections.
Hi h Pressure Coolant In ection Pi in There are 16 (Units 1 and 2) and 14 (Unit 3) Class 1 circumferential pressure retaining welds and 4 (Unit 1, 2, and 3) pipe whip protection welds in the high pressure coolant injection system subject to examination. The-system-i~-carbon-steel . A-total =
of 4 (Units 1, 2, and 3) circumferential welds (approximately 25 percent) and 4 (Units 1, 2, and 3)
BFNP Sl"4.6.G Page 15 SEP 29 1981.
pipe whip protection welds (100 percent) shall be examined during the inspection interval. See Table A of Appendix A for weld size and scheduled inspectio'ns. The pipe whip protection welds are also scheduled in Table A and are listed individually in Table C of Appendix A.
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 under consideration.
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.
7.4 'i See Table A of Appendix A for scheduled inspections.
in 7.4.1 Su orts Inte rail and Han ers Welded Su Includes Valve ort Su Attachments orts There are 102 integrally welded supports on each unit in the Class 1 piping systems subject to examination. A total of 26 supports (approximately 25 percent) on each unit shall be examined during the inspection interval. Two integrally welded supports (KR-1-54 and KR-1-55) can be ultrasonically examined. The other integrally welded supports will be given a surface examination in place of an ultrasonic examination (See Request for Relief ISI-9).
See Table A of Appendix A for scheduled inspections.
r 7.4.2 Su ort, Com onents There are 121 support components (integrally welded and nonintegrally welded) on each unit in the Class 1 piping systems subject to examination.
All the components on each unit shall be visually examined during the inspection interval. The examination shall extend from the piping or valve attachment to and including the attachment to the supporting structure. The settings of any spring type hangers, snubbers, and shock absorbers shall be verified. See Table A of Appendix A for scheduled inspections.
BFNP SI-4.6.6 Page 16 SEP 29 1981 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 CFSM). The requirement for visual examination of the pump internal pressure boundary surfaces is waived unless the pump is disassembled for required maintenance (See Request for Relief ISI-4).
The alternate inspe'ction is a visual examination if the internal surfaces are made accessible during maintenance. If during the 10-year interval a pump from any unit is not disassembled, a pump from one unit shall be examined from the exterior. This shall be accomplished by taking ultrasonic thickness measurements of the pump casing. Disassembly of the pump is in accordance with MMI-21 and provides for the examinations listed. See Table A of Appendix A for scheduled inspections.
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 schedyled inspections.
7 ' ' 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 inspections.
7.6 Valve Pressure Bounda 7.6.1 Valve Bod Seam Welds None of the valves in any of the Class 1 piping systems under consideration have body seam welds.
They are all single-piece cast construction.
BFNP SI-4.6.G Page 17 SEP 23 '1981 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. Visual examinations of internal pressure boundary surfaces during routine maintenance is perf'ormed and documented under existing plant administrative procedures (See Request for Relief ISI-5). The existing plant procedures are listed below:
~ MMI-13 Main Steam Relief Valves MMI-17 Main Steam Isolation Valves MMI"51 CSSC Valve Maintenance MMI-57 Recirculation Pump Discharge Valves MMI"77 Main Steam Safety Valves The plant personnel responsible for the maintenance of the valves shall also send"a copy of the completed data sheet to the NCO QA Staff 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 will be made to determine the practicality of disas" sembling a valve from one of the multiple units solely for visual examination. If necessary, a request for relief will be issued at that time.
Valve Pressure Retainin Boltin None of tbe 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 60 valves (on each unit) with bolting smaller than 2 inches. The examinations will be distributed equally among the three 40-month cycles of the inspection interval.
The valves are listed in Table 7.6,3"1. See Table A of Appendix A for scheduled inspections.
uxnr SI-4-.6 0 Page 18 SE;I'29 1981
~
7.6.3-1 TABLE System Valve Numbers (Flow Diagram Number)
Feedwater 96A (3-554), 28A (3-558), 29A (HCV 3-67), 96B (3-568),
28B (3-572)1 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 1-38, 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) 74"691, FCV 74-78)
FCV 74-77 CRD Return 85-77 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 RCIC FCV 71-40 HPCX FCV 73-2, FCV 73-3, FCV 73-45
BFNP SI-4.6.6 Page 19 SEP 29 1981 7.7 Exem ted Com onents The components exempted from volumetric and surface examination shall be visually examined during system pressure tests in accordance with IWA-5000 and IWB-5000 of ASME Section XI (see Section 7.0). The pressure tests are implemented by Surveillance Instruction 3.3.
8.0 COMPONENTS SUBJECT TO EXAMINATION"TVACLASS 2 The Class 2 components 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. The Metallurgy and Standards Group shall select areas to be examined or the NCO QA Staff may assist in selecting areas to be exa'mined.
Components that are exempted from examination in accordance with IWC-1220 of ASME Section XI are discussed in Section 7.7 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.
Examinations that reveal unacceptable structural defects in a category and in one multiple stream of the system shall be extended to include an additional number (or areas) of components in the same category approximately equal to that number initially examined. In the event further unacceptable structural defects are revealed, all of the 'same component(s) in the other multiple streams of the system shall be. examined.
Bolting larger than two inches in diameter shall be ultrasonically examined (Request for Relief ISI-14).
Examinations of Class 2 components began during the first 40-month cycle of the inspection interval on Unit 3 and will begin 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
BFNP S1-4.6.G Page 20 SEP 29 1981 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 ultrasonically examined during the inspection interval. The welds shall be selected from two different heat exchangers. The exami-nations shall cover at least 20 percent of each circumferential weld selected for examination, uniformly distributed among three areas around the vessel circumference.'ee Table B of Appendix A for scheduled inspections.
The shell and shell cover sections are fabricated to A-515, GR.70. Flange sections are fabricated to A-105, GR.II.
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 reinforce-ment ring covering the nozzle-to-shell weld (see Request for Relief ISI-13). The alternate inspection will be a surface examination of the reinforcement ring welds. A total of one rein-forcement ring weld (weld to the nozzle and to the shell) from the four MIR heat exchangers shall be surface examined during the inspection interval.
The weld selected for examination shall be located on a different RHR Hx than those selected for examination in accordance with Section 8.1.1.
See Table.B of Appendix A for scheduled inspections.
The reinforcement rings are fabricated to A-515, GR.70.
RHR Hx Su ort Attachments There are 3 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 inspections..
The support attachments are fabricated to ASTM A-283 Gr.D or equal.
BFNP SI-4.6.G Page 21 SFP 23 198) 8.1.4 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 Request for Relief ISI-14).
The studs and nuts are fabricated to A-193 Gr.B7 and A-194 Gr.2H, respectively.
8.2 Pi in Pressure Bounda The areas to be examined include circumferential pipe welds, 4 inches diameter and larger, 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, 4 inches diameter and larger.
The weld totals are for unit 3; separate totals for units 1 and 2 will be included as soon as the weld maps are verified by walkdown (Class B welds were not required to be examined during the first cycle of units 1 and 2) ~
8.2.1 Main Steam Pi in There are 74 Class 2 circumferential and branch connection pressure boundary pipe joint welds subject to examination. Approximately 15 of these welds will be ultrasonically examined during the first inservice inspection interval and 59 welds during the 40-year inspection program. The examinations during the first 10-year interval will be one 26 inch weld and three 24 inch welds from the four steam lines, two 24 inch welds and one 18 inch w'eld from the steam header and loop, five 6 inch welds (including branch connection) from the auxiliary steam line, and three 6 inch welds from the three auxiliary steam branch lines.
The welds selected will be distributed among the different streams so as to effectively examine all welds of one stream. See Table B of Appendix A for weld size and scheduled inspections.
BFNP SI-4.6.G Page 22 SEP S9 198l 8 '.2 Residual Heat Removal Pi in There are 380 Class 2 circumferential an'd branch connection pressure boundary pipe joint welds subject to examination. Approximately 46 of these welds will be examined during the first inservice inspection interval and 170 welds during the 40-year inspection program. See Table B of Appendix A for weld size and scheduled inspections.
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 (l-l/4 inches) and 48 nuts. The bolting is less than two inches in diameter (see Request for Relief ISI-14).
The studs and nuts are fabricated to A-193 Gr.B7 and 8.4 'i A-194 Gr.2H, in Su respectively.
orts and Han ers (Includes Valve Su orts) 8.4.1 Inte rail Welded Su ort Attachments There are 104 integrally welded supports on each unit in the Class 2 piping systems. A total of 46 selected supports on each unit shall be surface examined during the inspection interval. See Table 8.4.1-1 for the selected hangers and Table B of Appendix A for the scheduled inspections.
Four of the restraints cannot be fully examined (see Request for Relief ISI-ll).
Table 8.4.1-1
~Ss tern H-4~7>9~10~12~14,17,18>22 24~27s29r31i 35,36,37,55,5SA)62,71,85,118,122,124, 145,145A,157, and 158 R 12~ 12A~35B~35C~36~37B~37C~50~53~
56, and 64 Main Steam RG 1ST ~ RG 2MSR ~ MSH 14 ~ MSGEH 1 MSGEH 2 ) MSH 17 ) HPASH 7
BOP SI-4.6.G Page 23 SEP 23 l981 8.4.2 Su ort Com onents There are 193 support components (integrally welded and nonintegrally welded) on each unit in the Class 2 piping systems subject to examination.
All the components on each unit shall be visually examined during the inspection interval. The examination shall extend from the piping or valve attachment to and including the attachment to the supporting structure. The settings of any spring-type hangers, snubbers, and shock absorbers shall be verified. See Table B of Appendix A for scheduled inspections.
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.
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 Request for Relief 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 inspections.
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 during system pressure tests in accordance with IWA-5000 and IWC-5000. The pressure tests are implemented by Surveillance, Instruction 3.3.
BFNP SI-4.6.G Page 24 SEP 29 1981 Exempted components are: a) components in systems where both the design pressure and temperature are equal to or less than 275 psig and 200 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.
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.
Supports and hangers 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 during the pressure tests to detect any loss of support capability, and evidence of inadequate restraint. The pressure tests are implemented by Surveillance Instruction 3.3.
Requirements are included in the Browns Ferry pressure test program, OQAM Part II, Section 5.1, Item 2.0 and Surveillance instruction 3.3.
10.0 AUTHORIZED INSPECTOR TVA shall employ an Authorized Inspector(s) in accordance with ASME Section XI for inservice examinations, repairs, and replacements of TVA Class 1, 2, and 3 components at Browns Ferry Nuclear Plant.
The Inspector 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 Af in accordance with IWA-2140 of ASME Section XI.
TVA's interface with the Authorized Inspector for inservice inspection, repairs, and replacements is defined in OQAM Part II, Section 5.1.
11.0 EXAMINATION METHODS Any nondestructive examination procedures shall meet the requirements stated in this section.
BFNP SI-4.6.G Page 25 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 Liquid penetrant examination shall be conducted in accordance with Article 6,Section V of the ASME Code.
11.3 Volumetric Examination 11.3.1 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 accordance with Article IWA-2232 of ASME Section XI, 1977 Edition, Summer 1978 Addenda (Piping) and Appendix I, 1974 Edition, Summer 1975 Addenda of ASME Section XI (Vessels).
Where Appendix I (I-1200) is not applicable; the provisions of Article 5,Section V of the ASME Code shall apply.
BFNP SI-4.6.G Page 26 SEP 2S 1981 12.0 UALIFICATIONS OF NONDESTRUCTIVE EXAMINATION PERSONNEL Personnel performing nondestructive examination operations shall be qualified in accordance with IWA-2300 of ASME Section XI (DPM'75C01).
13.0 ACCEPTANCE CRITERIA All acceptance standards for Class 1, 2, and 3 components shall be in accordance with IWA-3000 of ASME Section XI.
14.0 REPAIRS AND REPLACEMENTS The repair and replacement program is in accordance with the 1977 Edition, Summer 1978 Addenda, of ASME Section XI.
ASME Section XI repairs and replacements may be coordinated as necessary with the Metallurgy and Standards Group of the Controls and Test Branch. Repairs and replacements which require NDE shall be coordinated with the NCO QA Staff. Any plant controlled weld map drawings which require revision as a result of a repair or replacement shall 'be submitted to the NCO Metallurgy and Standards Group.
14.1 ~Re airs This section provides requirements for repair of the pressure retaining boundary of ASME Class 1, 2, and 3 components (and their supports). The repair program is included in OQAM Part II, Section 2.1.
Repairs shall be performed in accordance with the Design Specification and Construction Code of the component or system. Later edition's of the Construction Code or Section III, either in its entirety or portions thereof, may be used. If repair welding cannot be performed in accordance with these requirements, the repair may be made in accordance with IWA<<4000 and IVB-4000, IWC-4000, or IWD-4000 as applicable.
Material shall conform to the requirements of either the original design specification or ASME Section III.
After repairs by welding on the pressure-retaining boundary of components, a hydrostatic pressure test shall be performed in accordance with IWA-5000 and IWB-5000, IWC-5000, or IWD-5000 as applicable of ASME Section XI. The following may be exempted from these pressure tests exclusive of those repairs employing a temper bead technique; Cladding repairs," '
(1)
'2)
Heat exchanger tube plugging,
BPNP SI"4.6.G Page 27 SEf 23 1981 (3) Piping, pump, and valve repairs .that do not penetrate through the pressure boundary, (4) Pressure vessel repairs where the repaired cavity does not exceed 10 percent of the minimum design wall thickness, and (5) Component connections, piping, and associated valves that are one-inch nominal pipe size and smaller.
Repaired areas shall be examined in accordance with applicable nondestructive methods to establish a preservice record (see Sections 7.0, 8.0, and 9.0). These examinations shall include the method that detected the flaw. If the repair is performed in accordance with the provisions of the code applicable to the construction of the component, any additional nondestructive examinations required by the construction code shall be performed (excluding pressure test requirements). The requirements are not applicable if the repair includes the complete removal or isolation of the item bearing the flaw, such as heat exchanger .
tube plugging.
The services of an Authorized Inspection Agency shall be used when making a repair. The ANI shall assure that the repair welding procedures and welders are qualified in accordance with IMA-4000 of ASNE Section XI. (See Section 10.0)
The records and reports of Section 15.0 shall be completed for all repairs.
This section provides requirements for replacements of ASME Class 1, 2, and 3 components. This program does not provide rules for the addition of complete systems.
Replacements shall meet the requirements of the Edition of the Constructiod Code to which the original component or part was constructed (the code edition and addenda shall be specified). Replacements ordered as spares for future use at an unspecified time should meet the requirements of the Construction Code Edition used for the original part or component that is intended to be replaced. DPI N76A10 shall be used as applicable.
Replacements for parts or components originally con-structed without code requirements shall be in accordance with the original design, fabrication, and inspection requirements for the part or component being replaced.
BFNP SI-4.6.G Sk.v 29 1981 Alternatively, replacements may meet all or portions of the requirements of later editions of the Construction Code, provided that the following requirements are met:
(1) The requirements affecting the design, fabrication, and examination of the replacement are reconciled with TVA's specification.
(2) Mechanical interfaces, fits, and tolerances that provide satisfactory performance are not changed by. the later edition of the Construction Code.
Modified or altered designs are reconciled with TVA's specification through the Stress Analysis Report, Design Report, or other suitable method which demonstrates the satisfactory use for the specified design and operating conditions, whichever is applicable.
(4) Materials are compatible with the installation and system requirements.
Prior to authorizing the installation of a replacement, an evaluation of the suitability of the replacement shall be conducted. If a replacement is required because of failure of a part or component, the evaluation shall consider cause(s) of failure of the existing part or component to assure that the selected replacement is suitable. If cause of failure appears to be a deficiency in the specification for the existing part or component, the specification for the replacement shall reflect appropriate corrective provisions.
Any such corrective provisions shall be consistent with relevant requirements of the Construction Code in effect at the time of- specification revision. The report of the evaluation shall be made a part of the replacement record.
Welding required for the installation of a replacement shall be performed by welders who are qualified in accordance with ASME Section IX, and by using procedures that are qualified in accordance with ASME Section IX and the additional heat treating and impact tests required by IWB-4000 of ASME Section XI.
The application of the ASME NA symbol stamp is neither required nor prohibited, for the installation of replacements.
BFNP SI-4.6.G Page 29 SEP 29 1981 The following items and parts are exempt from the requirements of this section:
(1) gaskets; (2) instruments; (3) electrical conducting and insulating material; (4) piping, valves, and fittings 1-inch nominal pipe size and less, except that materials and primary stress levels shall be consistent with the requirements of the applicable Construction Code.
Detailed stress analysis and consideration of secondary stress is not required; (5), nonstructural pump and valve internals except when the original equipment was constructed in with a Construction Code or Code Case;
'ccordance (6) pump seal package and valve packing.
The following reports and records shall, to the extent required by the Construction Code and this section, be maintained by TVA, as applicable:
(1) Certified Design Specification (2) Certified Stress Report (3) Design Report (4) Overpressure Protection Report (5) Manufacturer's Data- Report (6) Material Certification (7) Evaluation Report of Replacements Revisions to existing reports, records, and specifications may be shown as an amendment, or as a supplement, and attached to the original record or report to provide an up-to-date record of the replacement.
A preservice inspection shall be made in accordance with IWB-2100, IWC-2100, and IWD-2100 of ASME Section XI for the component and part replaced, as applicable, and including the joints that connect the replaced component or part to the system, prior to return of the plant to service.
BFNP SI"4.6.G Page 30 SEP 2S 1981 Installation of Re lacements - TVA Class 1 Flanged joints may be used in piping systems.
Extended joints shall not be used in piping systems.
Threaded joints in which the threads provide the only seal shall not be used in pipe joint configura-tions. If a seal weld is employed as the sealing medium, the stress analysis of the joint shall include the stresses in the veld resulting from the relative deflections of the mated parts.
Flared, flareless, and compression-type tubing fittings may be used for tubing sizes not exceeding 1-inch O.D. within the limitations of applicable standards and requirements {2) and (3) below. In the absence of such standards or specifications, the cognizant engineer shall determine that the type of fitting selected is adequate and safe for the design conditions in accordance with the following requirements:
(1) The design pressure or pressure ratings shall be reconciled with TVA's specifications.
(2) Fittings and their joints shall be suitable for the tubing with which they are to be used in accordance with the minimum wall thickness of the tubing and method of assembly recommended by the manufacturer.
(3) Fittings shall not be used in services that exceed the manufacturer's maximum pressure-.temperature recommendations.
V (4) Fittings shall be installed in accordance vith the manufacturer's recommendations.
The methods of ASIDE Section III, Appendix E, shall be used to determine bolt size and torquing loads, unless mating parts built to other requirements make this impractical.
The rules and requirements of Section 14.0 shall apply to the attaching of replacements to the system where such attachment is by welding.
SFNP SI-4.6.G Page 31 SEP 29 1981 Materials shall comply with the requirements to which the original component or part was constructed. As an alternative, materials may comply with the requirements of ASME Section III, NB-2000 provided the requirements of Section 14.2 are met.
Installation of Re lacements - TVA Class 2 Nonwelded piping joints shall meet the require-ments of NC-3671 of ASME Section III.
The methods of ASME Section III, Appendix E, shall be used to determine bolt size and torquing loads, unless mating parts built to other requirements make this impractical.
The rules and requirements of Section 14.0 shall apply to the attaching of replacements to the system where such attachment is by welding.
Materials shall comply with the requirements to which the original component or part was constructed. As an alternative, materials may comply with the requirements of ASME Section III, NC-2000 provided the requirements of Section 14.2 are met.
r Installation of Re lacements - TVA Class 3 Nonwelded piping joints shall meet the requirements of ND-3671.
The methods of ASME Section III, Appendix E, shall be used to determine bolt size and torquing loads, unless mating parts built to other requirements make this impractical.
The rules and requirements of Section 14.0 shall apply to the attaching of replacements to the system where such attachment is by welding.
Materials shall comply with the requirements to which the original component or part was constructed. As an alternative, materials may comply with the requirements of ASME Section III, ND-2000 provided the requirements of Section 14.2 are met.
BFNP SI-4.6.G Page 32 SEP 23 1981 15.0 RECORDS AND REPORTS 15.1 Recordin and Re ort of Examinations A detailed report of all examinations shall be prepared by the performing or responsible organization and should contain but not be limited to the following information:
(1) Date and time of examination.
(2) Identification of part examined including wall thickness (if applicable), type material, part temperature, and unit identification.
(3) Identification of examiner and level of certification.
(4) Type of examination (PT, UT, etc.) and specific NDE procedure used.
(5) Certification of NDE materials such as penetrant, couplant, etc.
(6) Results of examination.
(7) Corrective action and repairs.
(8) MGTE and inspection equipment used and their calibration due dates.
(9) For eddy current examination of heat exchanger tubing, the report shall include a record indicating the tube(s) examined (this may be marked on a tube sheet sketch or drawing), the extent to which each tube was examined, the location and depth of each reported indication, and the identification of operator(s) and data evaluator(s) who conducted. each. examination or part thereof.
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' marked drawing or sketch shall indicate the weld or part examined. Information should also include all other pertinent data that would later permit duplication or relocation of a flaw, such as transducer type, size, shape, frequency, beam angle, couplant, and distances from some given reference points.
BFNP SI-4.6.G Page 33 SEP 29 1981.
All required and pertinent information will be recorded on the appropriate data sheets by the performing organization.
When portions of the inspection work are contracted, a detailed report will be submitted to TVA by the contractor with all pertinent and required information. TVA will retain the original copies of all raw data taken.
The NCO QA Staff shall review and submit the final report to the Plant Superintendent for review. Data Sheet 1 in Appendix F will be completed and used as a cover sheet for the final report and to document the review process.
15.2 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 inservice inspection with the Nuclear Regulatory Commission Region II Office in accordance with IWA-6220, ASME Section XI.
The ISI report shall have a cover sheet providing .the fol-lowing information:
(1) Date (2) Name of owner and address of corporate offices (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 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 or part numbers and such information regarding manufacturer's'omponent 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.
BFNP SI"4.6.G Page 34 SEP 2> ~SSl (4) Date of completion of the inservice inspection.
(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.
The ISI Report shall have an owner's data report for inservice inspection, Form NIS-1 as shown in Appendix II of ASME Section XI.
15.3 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 15.4 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 correctime actions taken.
16.0 NOTIFICATION OF INDICATION Plant management shall be formally notified of the presence of unacceptable indications detected during the performance of nondestructive examinations. Unacceptable indications are defined by the applicable NDE procedure. Formal notification shall consist of completing and submitting to the Plant Superintendent the "Notification of Indication" form in Appendix D of this program.
BFNP SI-4.6.G Page 35 SEP 8> 1981 Part I of the "Notification of Indication" shall be completed and signed by the NDE Ievel II or III examiner detecting the indication.
The Baseline and ISI Section representative of the NCO QA Staff shall review and sign the form. If the indication is detected by an outside contractor, the contractor's field supervisor shall review and sign the form.
Part XI of the form shall be completed for evaluation of findings by a TVA NDE Level III individual. This individual shall indicate under "Disposition" his recommended disposition of the indication.
He shall reference examination procedures to be usedf reexami-nation is a requirement. He shill then sign and date the form.
Copies of the form shall be distributed to the Plant Superintendent, the Baseline and ISI Section Representative, the Metallurgy and Standards One copy Group, and, if appropriate, the Plant Outage Director.
shall be filed with the examination report.
Upon receipt of the Notification of Indication form, the Plant, Superintendent shall be responsible for determining the organization to implement the disposition. The Plant Superintendent or his representative shall be responsible for preparing instructions to repair the indication in accordance with N-OQAM, Part XI, Section 2.1, and the recommended disposition on the form. Dispositions other than restoring to original requirements shall be processed as modifications in accordance with N-OQAM, Part II, Section 3.0. The plant shall coordinate with the NCO QA Staff to conduct reexamination when reexamination is a requirement. Additionally, coordination with the AIA representative shall be made, when appropriate, as follows:
- a. Make available to the ANII any records he needs to accomplish his duties.
- b. Give adequate notice to the AIA that, an ANII and/or ANX will be required for repair work.
Detailed requirements for interfacing with the AIA for repairs to code items are contained in N"OQAM, Part II, Section 2.3.
Upon completion of the action required to repair the indication',
the Baseline and ISI Section representative of the NCO QA Staff shall review the repair instructions to assure completion, and shall sign and date the Notification of Xndication Form, Part II.
The review shall:- include referencing the repair instructions on the completed form. The signed form shall remain with the examination report for use as a quality assurance record. In addition, if the component requires reexamination, one copy of the completed form shall be filed with the new examination report.
The reexamination report number shall also be referenced on the completed form by the Baseline and ISI Section representative.
'dditional distribution of the form shall be performed as noted for Part IX of the form.
BFNP SI-4.6.G Page 36 SEP 29 19S1 17.0 CALIBRATION BLOCKS Many of the basic calibration blocks used for examinations at Browns Ferry were fabricated to the 1971 Edition of ASME Section XX.
These blocks will continue to be used for XSI work (see Request for Relief ISX-10). See Appendix C for calibration block drawings.
The plant QA Staff shall be responsible for storage and control of the calibration blocks onsite as required in Appendix I, I-3150, of ASME Section XI.
The NCO QA Staff shall maintain as-built calibration block drawings.
Copies of the original drawings and any revisions shall be submitted to the Metallurgy and Standards Group.
18.0 RE UESTS FOR RELIEF Where TVA has determined that certain code requirements or examinations are impractical, TVA will submit written requests for relief 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 requests for relief shall be included.
When impractical examination requirements are identified in the field, the NCO QA Staff shall notify the Metallurgy and Standards Group such that the information may be included in this program and requests for relief may be prepared if necessary.
The requests for relief are listed in Appendix G. The current requests for relief are ISX-2 through ISI-15 'hose requiring alternate inspection are XSI-4 through ISI-10, ISI-13, and ISI-15.
19.0 AUGMENTED INSPECTIONS Augmented inspections are performed in addition to ASME Section XI code requirements. The augmented inspections may be required by the NRC or self-imposed 6y TVb. Appendix E contains tables of augmented inspections performed for Sections 19.1, 19.2, 19.6, and 19.7.
19.1 Feedwater Nozzles The augmented examination of the feedwater nozzles is included in DPM-BF77M2 (NUREG-0312) and updated in NUREG-0619.
The requirements are an ultrasonic examination of all the feedwater nozzle safe ends, bores, and inside blend radii every second refueling outage. The feedwater spargers shall be visually examined every fourth refueling outage (MMI 14.3-A).
A routine liquid penetrant'examination shall be performed every ninth refueling outage or every 135 startup/shutdown cycles'.
BFNP SI-4.6.G Page 37 If any indications are found in the safe end they shall be evaluated per ASME Section XI. If any recordable indications (defined in ASME Section V, Article 4, Paragraph T-441.8) are interpreted to be cracks in any nozzle, the nozzle bore and blend radii shall be liquid penetrant examined and repaired if necessary. If any cracks are detected, remove all spargers and completely examine all nozzles, and remove all nozzle cracks.
Reporting is required within 6 months of completing an outage during which an inspection was performed. Refer to NUREG-0619, Section 4.4.3 for information to be included.
19.2 Core S ra Pi in The augmented examination requirements of stainless steel Class 1 core spray piping is included in DPM BF76M7 (NUREG-0313 issued for comment). The stainless steel welds to the second isolation valve shall be ultrasonically examined for three successive intervals. If no unacceptable indications are found, the examination frequency may revert to the scheduled ASME Section XI inservice inspections.
Results to be sent with final report (section 15.0).
19.3 Core S ra S ar ers The augmented examination requirements of the core spray spargers is included in MMI 14.3-A, which implements IE Bulletin 80-13. The spargers shall be visually examined each refueling outage. Volumetric techniques may be used to evaluate any indications'he reporting criteria is listed in MMI 14.3-A. If cracks 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.
19.4 Recirculation Pressure Test Connections The augmented examination requirements of the one inch pressure test connections on the recirculation suction lines is included in DPM BF76M7 (NUREG-0313 issued for comment). The one inch pressure test connection welds shall be given a liquid penetrant'or visual examination for three successive intervals. Xf no indications are found the examinations may be discontinued. Results to be sent with final report (section 15.0).
BFNP SI-4.6.G Page 38 SEf'3 198]
19.5 Jet Pum Assemblies and Holddown Beam The augmented examination requirements of the jet pump assemblies are included in MMI 14.3-A, which implements IE Bulletin 80-07. Each jet pump assembly shall be visually examined each refueling outage per the requirements in MMI 14.3-A. 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.
The NRC regional office is to be promptly notified following completion of the inspection and a report issued to the NRC within 14 days.
19.6 CRD Return Line Reroute The augmented examination requirements of the CRD return line reroute are included in NUREG 0619. The requirements are a final liqu'id penetrant. examination of the capped nozzle.
Also, the welded connection joining the rerouted CRD return line to the reactor water cleanup system shall be ultrasonically examined each refueling outage. The weld, RCRD-1-45 (Units 2 and 3 also), will 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. Welds RCRDS-1-3 and RCRD-1-44 (Units 2 and 3 also) shall be ultrasonically examined along with the pipe on the downstream side.
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.
19.7 Reactor Water Cleanu The augmented examination requirements of the reactor water cleanup line are TVA imposed and are included in J. G. Dewease's memorandum to H. L. Abercrombie (L26 791227 833). The reactor water cleanup welds shall be ultrasonically examined from the RHR connection to the primary containment penetration (X-14).
The examinations shall be performed each refueling outage or until there are no unacceptable indications for three successive outages at which time the examination frequency may revert to the scheduled ASliE Section XI requirements.
Report to be submitted with final inservice report (section 15.0).
4
BFNP SI-4.6.0 Page 39 SEf'29 198l 19.8 Evaluation of Corrosion Dama e of Pi in Com onents Ex osed to Residue from the March 22 1975 Fire The augmented examination requirements of piping components exposed to residue from the March 22, 1975, fire are 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 will be the responsibility of the NCO QA Staff. The metallurgical analysis required will be the.
responsibility of the Metallurgy and Standards Group.
The examination of the piping components exposed to residue from the March 22, 1975, fire is a technical specification requirement (4.6.G.6).
A report is required each outage upon completion of the examinations. The data sheet is included in the instruction.
20.0 REFERENCES
20.1 ASME Boiler and Pressure Vessel Code--Section XI through Summer 1975 Addenda.
20.2 ASME Boiler and Pressure Vessel Code--Section V.
20.3 Browns Ferry Nuclear Plant Final Safety Analysis Report.
20.4 Browns Ferry Nuclear Plant Operational Quality Assurance Manual Part II, Sections 2.0, 3.0, 4.0, 5.0, and 6.0.
20.5 Browns Ferry Nuclear Plant Technical Specifications.
20.6 BRW Reactor Pressure Vessel Manual--Contract 66C60-90744, NIM-131-1A.(2).
20.7 BRJ--Recirculation Pump'anual--Contract 67C60-91750, NIM-132-2A.
20.8 Bingham Pump Co.--RHR Pump Manual--Contract 66C60-90744, NIM-131-1D(4).
20.9 Perfex Heat Exch.--RHR Ht Exchanger Manual--Contract 66C60-90744, NIM-131-1.
20.10 Division Procedure Manuals N80E3 and N75COl.
BFNP S1-4.6.G Page 40 SEP 28 1981 APPENDIX A
TABLE A (UNIT 1)
BROWS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 - Exam Dose Rate
~Com onent ~Sam le ~Sam le ~of lna Month Month Month 'Cate ott ~4th C cle Remarks A. "Reactor Vessel Seam welds not in Core Region r
- a. Circumferential 28 ft. 7 ft. UT 2 ft. 2 ft. 3 ft. B-B 10 CHM-992-C
- b. Longitudinal 23.6 ft. 5.9 ft. UT 1.9 ft. 2 ft. 2 ft. B-B 10 CHM-1095-A I2. Closure Head Seam Meld 8 ft. 2 ft. UT .5 ft. 1 ft. B-B 10 CHM-1095-A
~3. Closure Head 24 ft. 6 ft. UT- 1 ft. 2 ft. 3 ft. B-B 10 CHM-1095-A
} Meridional Weld I4. Vess'el-to-Flange 69 ft. 69 ft. UT 23 ft. 23 ft. 23 ft. B-C 10 CHM-1095-A i ~
Circumferential Meld I
5'. Head-to-Flange 66 fp. 66 ft. UT 22 ft. 22 ft. 22 ft. B-C 10 CHM-1095-A Circumferential Meld I I I
6, Primary Nozzles I
Main Steam (26")
- a. Nozzle-to-Vessel 20 CHM-1094-A.
';and Inside Radii Sheet 1
- b. nozzle-to-Safe End B-J I
Core. Spray (10")
- a. Pfozzle-to-Vessel B-D 100 CHM-1094-A
!and Inside Radii
! b. /ozzie-to-Safe End UT, PT B-F l
CA Pl
~%Mt'+
~e 00
~w A
OO
TABLE A (UNIT 1, CONTINUED)
BROGANS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com onent ~Sam le S~am le ~of Ina Month Month Month Cate~os ~4th C cle Remarks Feedwater (12")
a: Nozzle-to-Vessel B-D 800 CHM-1094-A and Inside Radii Sheet 1
- b. Nozzle-to-Safe End B"J Recirculation Inlet (12'I) a". Nozzle-to-Vessel 10 10 UT B-D 200 CHM-1094-A and Inside Radii Sheet 1
(28tf)
- a. Nozzle-to-Vessel 2 n 2 UT B-D 100 CHM"1094-A and Inside Radii Sheet 2
- b. Nozzle-to-Safe End 2 2 B-F a
Jet Pump Instr. (4")
- a. Nozzle-to-Vessel UT B-D 500 CHM"1094-A and Inside Radii Sheet 3
- a. Nozzle-to-Vessel B-D 50 CHM"1094-A and Inside Radii Sheet 5
A
TABLE A (UNIT 1, CONTINUED)
BROWS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com oncet ~Sam le Sama le ~of lns Month Month Month ~Cate orR 4th Ctcle Remarks Head Instr. (6
- a. Nozzle-to-Vessel B-D 10 CHM"1094-A and Inside Radii Sheet 6
- b. Nozzle-to-Flange B-J Head Vent (4")
- a. Nozzle-to-Vessel B-D 10 CHM"1094-A and Inside Radii Sheet 7
- b. Nozzle-to-Flange B-J
- 7. Closure Nuts 92 30 30 32 B-G" 1 5 CHM"2001-A
- 8. Closure Studs 92 92 UT 30 30 32 B-G-1 5 4 4 MT 4 B-G-1 5 See Section 6.1.3 9! Closure ushers 92 92 30 30 32 B-G-l 5 and Bushings 4 4 4 B-G"1 5 See Section 6.1.3 10: Ligaments between 92 92 30 30 32 B-G-1 10 Threaded Stud Holes ll. CRD Housing fields 40 40 Inspection During B-0 Request for I System Pressure Tests Relief ISI-6 1
I 12.'essel s
Penetrations 63 63 VT Inspection During B-E 20 System Pressure Tests
- 13. Support Skirt 4 ft. 4 ft. UT 1 ft. 1 ft. 2 ft. B-H 20 CHM-1091-A to Vessel Meld
- 14. Vessel Cladding 6 Patches 6 Patches VT 2 2 B-I-1 10 15; Internals General Surveillance B-N-1) 10 BF MMI-14.3-A B-N-2 tlCh &
00 0 4 '0 Z
c o A
CC7 OO
TABLE A (UNIT 1, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com onent ~Ram le ~Ram le ~of Ins Month Month Month ~Cate or ~4th C cle Remarks B. Piping
- l. Recirculation 20 CHM-1081-C Circumferential 28" SS 33 8 2 3 B-J 22'ISS 10 3 1 1 B-J 12"SS 40 10 4 3 B-J 4'ISS 5 1 1 B-J Branch Pipe Connection Welds 12"SS 8 UT B-J 4"SS 7 PT B-J
- 2. 'Main Steam 30 CHM-1082"C Circumferential Four Welds Inaccessibl 26" CS 54 14 5 5 B-J (KMS-l-l, 26"CS (Pipe Whip) 6 6 2 2 B-J KMS-1-81) 6"cs 50 13 4 4 B-J KMS-1"29 6 KHS-1-56)
See Table C Branch Pipe Connection Welds 10" CS 1 1 UT 1 B-J 6IICS 25 6 PT or MT 2 .B-J 3II CS 1 1 PT or MT B-J P1 ~w~
PQ IIk CC)
OO
TABLE A (UNIT 1, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com anent Samale ~Sam le ~of lna Month Month Month Cate~os 4~th C ele Remarks l3 ~ Feedwater 30- CHM-1080-C Circumferential 100 Two Welds Inaccessible 24>>CS 25 6 2 ~
2 2 B-J (KFW-1-4, 2:
20>>CS 6 2 1 1 B-J KFW-1-22) 12>>CS 26 7 2 3 2 B-J See Request 12>>CS (Pipe Whip) 10 10 4 4 B-J for Relief ISI-8 (GFW-I-7, GFW"1-24)
See Table C Branch Pipe Connection Welds I
'l Core~
I Spray Circbmferential 75 CHM"1089-C Two Welds Inaccessible 12>>SS 23 UT B-J (DSC-1-12A, 12>>SS (Pipe Whip) 4 UT B-J DSC-1-4A) 10>>SS 4 UT B-J See Table C I
RHR I 30 CHM-1088-C Circumferential Three Welds Inaccessible 24>>SS 22 5 UT B-J (TRHR-1-192, 24>>SS (Pipe Whip) 3 3 UT B-J DRHR"1-3B, 20>>SS 7 2 UT B-J DRHR-1-13B) 20>>Dj.ssimilar 1 1 UT, PT B-F See Table C 20>>CS 2 1 UT B-J 6>>SS 26 7 UT B-J cn M 6"Dissimilar 1 1 UT, PT B-F 0) H<
A
'O CC)
TABLE A (UNIT 1, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com onset Samale Samale ~of Ins Month Month Month ~Cate ~o ~4th C ele Remarks
- 3. Feedwater 30- CHM-1080-C Circumferential 100 Two Welds Inaccessible 24"CS 25 6 2 2 . 2 B-J (KFW-1-4, 20"CS 6 2 1 1 B-J KFW-1-22) 12"CS 26 7 2 3 2 B-J See Request 12IICS (Pipe Whip) 10 10 2 4 4 B-J for Relief ISI-8 (GFW-1-7, GFW-1-24)
See Table C Branch Pipe Connection Welds 16"CS 1 B"J 8"CS 1 B-J s
I
~
4 Core Spray 75 CHM-1089-C Circumferential Two Welds Inaccessible 12"SS 23 B-J (DSC-1-12A, 12"SS (Pipe Whip) 4 B-J DSC"1-4A) 10"SS 4 B-J See Table C RHR 30 CHM-1088-C Circumferential Three Welds Inaccessible 24"SS 22 5 UT 2- B-J (TRHR"1"192s 24"SS (Pipe Whip) 3 3 UT 1 B-J DER-1-3B, 20"SS 7 2 UT 1 B-J DRHR-1-13B) 20"Dissimilar 1 1 UT,PT B-F See Table C I 20"CS 2 1 UT B-J I 6"SS 26 7 UT B-J Cn 6"Dissimilar 1 1, UT,PT B-F I 6"CS 4 1 UT B-J I
CD Ln ~
A Q3 CO
TABLE A (UNIT 1, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Area Quantity Inspected Dose Rate 40 Year 10 Year Method 40 80 120 Exam 4th Cycle
'Con onent S~am le S~am le ~of lns Honth Honth Honth ~Cate or (MR/HR) Remarks30-250 Pipe and Valve Supports and Hangers B-K-1 for
- a. Integrally Welded 100 25 MT or PT 8 Request 2 1 UT 1 B-K-1 Relief ISI-9, KR-1-54, and KR-1-55 b.'- Support Components 121 121 35 40 46 B-K-2 Integrally welded hangers are included I
Pressure Retaining 32 32 VT, UT 10 '0 12 B-G-l 30 Studs'uts 32 32 MT VT 10'0 When Removed 12 B-G-1 30 2 Ligaments Between 32 32 When connection is B-G-1 30 Threaded Stud Ht les disassembled i
I Welded 1' B-K-1 30
- 3. Integrally B-K-1 Supports
'i
- 4. Pump i
Casing VT During Normal B-L-2 Request for I
Maintenance Relief ISI-4 ll Valv.es 1 Valve, Bodies 60 During Normal B-M-2 Req est for Maintenance Rel ISI I
2.~ Pressure I
Retaining 60 60 20 ..20 -'0 B"G-2 Bolting a i OO
TABLE A (UNIT 1, CONTINUED)
BROWS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Area guantity Inspected Dose Rate 40 Year 10 Year Nethod 40 80 120 Exam 4th Cycle
~Com oncet ~Sam le ~Sam le ~of Ins Month heath Neath CategoOr (HRIHR) Remarks E. Exempt Components Inspection During B-P See Section Hydrostatic Testing 6.7
TABLE B (UNIT 1)
BROWNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com onent Samale S~am le ~of lns Month Month Month ~Cate orr 4th Ctcle Remarks A. RHR He'at Exchan ers
.5 .5 ft UT .5 ft C-A Bottom Head Flg. Weld (RHRG"11)
- 2. Nozzle to Vessel MT or PT C-B Request for Welds Relief ISI-13 Integrally Welded MT or PT C"C Supports I
ann Steam Pi in 20 CHM-2690-C I
Circumferential Welds 26" CS 2 1 1 C-F 24" CS 18 5 1 2 C-F 18" CS 10 2 1 C-F 6" CS 28. 7 2 2 C-F t
2.I Branch Pipe Connection Weld '
a 6" CS C-F CA 4
fS Cfi M
ASS 00 I
4o ~
A 1 OO a
I I
TABLE B (UNIT 1, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com onent ~Ssm le Soma le ~oi lns Month Month Month ~Cote or ~4th C ele Remarks C. R~RR Pi in 5-40 1; Circumferential Welds 24"CS 40 10 C-F 20"CS 53 14 4 C-F 18"CS 20 6 2 .C-F 164'CS 14"CS ll 3 1 C-F C-F 9 2 1 12"CS 1 . 1 C-F 10"CS 10 3 1 C-F 6"CS 18 5 2 C-F I
~
Pi in and Valve Su orts and Han ers I
Integrally Welded s Supports 46 PT or MT 12 14 20 C-E-1 See Table 8.4.1-1
- 2. Support Components 193 193 VT 50 70 73 C"E-2 R R~RR.Pnm s
- 2. Support Components 16 4 C-E-2 F. Ex t Co onents Inspection During Section 8.6 Hydrostatic Testing Cn CRi
~Rid+
00 e C'lR 1
Vl ot I O ~
A 1
I QO
,CQ
TABLE A (UNIT 2)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 ~
Exam Dose Rate Componenta Samale ~Sam le ~of lna Month Month Month ~Cate or ~4th C cle Remarks A. Reactor Vessel
'. Seam Melds Not Core Region In
- a. Circumferential 28 ft. 7 ft. UT 2 ft. 3 ft. B-B 10 CHM-2046-C
- b. Longitudinal 23.6 ft. 5.9 ft. UT 2 ft. 2 ft. B-B 10 CHM-1095-A
- 2. Closure Head Seam Weld 8 ft. 2 ft. UT 1 ft. B-B 10'0 CHM-1095-A
- 3. Closure Head Meridional 24 ft. 6 ft. UT 1 ft. 2 ft. 3 ft. B-B CHM-1095-A Weld
- 4. Vessel-To-Flange Circumferential Meld 69 ft. 69 ft. UT 23 ft. 23 ft. 23 ft. B-C 10 CHM-1095-A I
- 5. Head-To-Flange t
I Circumferential Weld 66 ft. 66 ft. UT 22 ft. 22 ft 22 ft. B-C 10 CHM-1095-A l
. I Primary Nozzles Main Steam (26") CHM-1094-A
- a. Nozzle-To-Vessel 2 B-D 20 Sheet 1 Iand Inside Radii
- b. 'Nozzle To-Safe End B-J Core Spray (10") 100 CHM-1094-A
- a. I Nozzle-To-Vessel B-D Sheet 1 and Ins'de Radii
- b. Nozzle-to-Safe End B-F Feedwater (12") 600-800 CHM-1094-A
- a. Nozzle-To-Vessel B-D Sheet and Inside Radii ca
- b. Nozzle-To-Safe End B-J Q'tl Ofl wc I
I QQ
TABLE A (UNIT 2, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com anent Samale S~am le ~of lna Sooth Sooth Sooth C~ate or ~4th C ale Remarks Recirculation Inlet 50-200 CHM-1094-A (12") Sheet 1
- a. Nozzle-to-Vessel 10 10 B-D and Inside Radii
- b. Nozzle-to-Safe End 10 10 B-F Recirculation Outlet 20"100 CHM"1094-A (28") Sheet I
- a. Nozzle-to-Vessel B-D ~
and Inside Radii
- b. Nozzle-to"Safe End B-F Jet Pump Instr. (4") 100-500 CHM-1094-A
- a. Nozzle-to-Vessel 2 t 2 Sheet 4 and Inside Radii
~~
- b. Nozzle-to-Safe End 2 I 2 I
CRD Hydraulic Return 50 CHM-1094-A (4") Sheet 5
- a. Nozzle-to-Vessel B-D and Inside Radii
- a. Nozzle-To-Vessel B-D 10 CHM-1094-A and Inside Radii Sheet 6
- b. Noizle-To-Flange B-J Head Vent (4")
- a. Nozzle-To-Vessel B"D 10 CHM-1094-A and Inside Radii Sheet 7 I b. Nozzle-To-Flange B-J I
- 7. Closure Nuts 92* 92 30 30 32 B"G-l CH5r5? 001" C P1 l U %CO Cf Ol M 04l I ID 4 I CC0 ~
CD
~a ~
TABLE A (UNIT 2, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COHPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com anent Sama le ~Sam le ~of Ins Month Month Neath Cater 4th Ctrcle Remarks
- 8. Closure Studs 92 92 UT 30 30 32 B-G-1 5-4 4 lfZ 4 B-G"1 5 See Section 6.1.3
- 9. Closure Washers and 92 92 30 30 32 B-G-1 and Bushings 4 4 4 B-G-l See Section 6.1;3
- 10. Iigaments Between 92 92 30 30 32 B-G-l 10 Thread Stud Holes ll. CRD Housing Welds 40 40 Inspection During B-0 50 Request for Hydrostatic Tests Relief ISI-6 12.'essel Penetrations 63 ,
63 Inspection During B"E 20 Hydrostatic Tests
- 13. Support Skirt To 4 ft. 4 ft. UT 1 ft. 1 ft. 2 ft. B-H 20 CHH-1091-A Vessel Weld
- 14. Vessel Cladding 6 patches 6 patches VT 2 2 B-I"1 10
- 15. Internals General Surveillance BN<<l, BN-2 10 BF MHI-14.3-A B. ~pi i~in I
Recirculation 20-100 CHH"2068"C
- a. Circumferential 28" SS 33 8 3 B-J I 22" SS 10 3 1 B-J 12" SS 40 . - 10 3 B-J 4" SS 5 1 B-J CIl 05
PT B-J B-J c
TABLE A (UNIT 2, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method .40 80 120 Exam Dose Rate Comoonent Samale Samale ~ot lns t oath Month tonth Cate~exp ~4th C rle Remarks Main Steam 30 CHM-2069-C a.'ircumferential Four Welds Inaccessible (KMS-2"1, KMS-2"81)
KHS-2"29, S KMS-2-56)
~ 26)'S 51 13 UT 4 4 5 B-J 26>> CS (Pipe Whip) 6 6 UT 2 2 2 B-J See Table C 6>> CS 50 13 UT 4 5 4 B-J
- b. Branch Pipe Connection fields 10>> CS B-J
'"6>>
3I'S CS 25, 1
1 1
6 1
2 2 1
B-J B-J Feedwater 30-100 CHM-2067-C
- a. Circumferential Two Welds, 24tt 25 6 UT 2 2 2 B-J Inaccessible
- 20) t 6 2 UT 1 1 B-J (KFV-2-4) 12tt 26 7 UT 2 3 2 B-J (KFW-2-22) 2>> (Pipe Whip) 10 10 UT 3 3 4 B-J See Table C
TABLE A (UNIT 2, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 CONPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Hethod 40 80 120 Exam Dose Rate
~Com onent ~Sam le ~Sam le ~of lns Roach Roach Roach CategoOr 4th Ctcle Remarks
- 4. Core Spray 75 . CHH-2071-C a ~ Circumferential 12" SS 10 3 UT 1 B-J 12" CS 2 UT B-J 12" Dissimilar 6 6 UT, PT 2 B-F 12" CS (Pipe Whip) 4 4 UT 1 B-J 10" SS 2 1 UT B-J 10" Dissimilar 2 2 UT, PT 1 B-F 10" CS 4 1 UT 1 B-J
- 5. 30 CHM"2070-C One Weld
- a. .Circumferential Inaccessible 24" SS 21 5 UT 2 2 B-J (TRHR-2-193) 24" SS (Pipe Whip) 3 3 UT 1 1 B-J See Table C 20" SS I 2 UT 1 B-J 20" Dissimilar 1 1 UT, PT B-F 20" CS 2 1 UT B-J 6" SS 24 6 UT 2 ~ B-J 6" Dissimilar 1 1 UT, PT B-F 6" CS 4 1 UT 1 B-J
- b. Branch Pipe Connection Weld 6" SS B-J
- 6. CRD Hydraulic Return 20 CHM-2072-C
, 4" SS 1, UT B-J Nozzle Cap~id ~M M ~
O 00 ~
O Ch Ln A s ~
'CO
TABLE A (UNIT 2, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120. Exam Dose Rate Comnonant ~Sam le Samale ~of Ens I onth I oath Month Cater ~4th C cle Remarks.
- a. Circumferential 6"
6" SS ll 3 2 B-J B-J SS (Pipe Whip) 4 4 2 See Table'C 4" CS 5 1 B-J
- 8. RCIC 20 CHM-2073-C
1 2
4
'TUT UT 2
2 B-J B-J B-J See Table. C
- 10. Bolted Connections ll. Pipe and Valve 20-250 Supports and Hangers
- a. Integrally Welded 100 25 MT or PT 8 B"K"1 Request for 2 1 UT 1 B-K-1 Relief ISI-9 KR-2-54 and KR-2-55
- b. Support Components 121 121 30 45 46 B"K-2 Integrally Welded Hangers ag Included Pl v a A
OQ
TABLE A (UNIT 2, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com anent S~am le S~am le ~of Ena Month Month Month ~Cate or ~4th C cle Remarks C. Recirculation Pum s 30
'1. Pressure Retaining 32 32 VTs UT j MT 10 10 12 B-.G-1 Studs When Removed Nuts 32 32 VT, 10 10 12 B"G-1 Ligaments Between 32 32 When Connection is B-G-1 30 Threaded Stud Holes Disassembled Integrally Welded UT 1 B-K-1 Supports VT 2 . 2 B-K-1 a
I Pump..Casing 2 During Normal B-L"2 Request for Maintenance Relief ISI-'4 I
a D. .Vatlves Valve Bodies 60 During Normal B-M-2 Request for Maintenance Relief
'ISI-5 2
'I P"'u e Retaining 60 60 20 20 20 B-G-2 Bolting I
em t Com onents Inspection During B-P See Hydrostatic Testing Section 6.7 rz U W m
Cfl H
EES I
OEE C '0 va ~
CO I
TABLE B (UNIT 2)
BROWNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS Estimated quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com oncet ~Ssm le ~Ssm le ~of Ins Month Month Month ~Cate <<os 4~th C cle Remarks A. RHR Heat Exchan ers I gs
.5 .5 ft UT C-A Bottom Head Flg. Weld (RHRG"11)
Circumferential Welds
~
- 1. s I
26" CS 2 1 UT 1 C"F 24" CS 18 5 UT 1 2 2 C-F 18" CS 10 2 UT 1 1 C"F 6" CS 28 7 UT 2 2 3 C-F
- 2. Branch Pipe Connection Weld 6" CS C"F
<<CS M IS<<
Q m
IJ<< Qs Qh ~
A
TABLE B (UNIT 2, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS I
~ S Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com onent Samale S~am le a~fina Month Month Month ~Cate oty ~4th C ele Remarks C. R~RR Pi in 5-40
- 1. Circumferential Welds 24"CS 40 10 3 4 C-F 20"CS 53 14 5 4 C-F 18"CS 20 6 2 2 C-F 16"CS 14"CS ll 3 1 1 C"F C-F 9 2 1 12"CS 1 1 C-F 10"CS 10 3 1 C-F
~ 6"CS 18 5 2 C"F I
D. Bi in and Valve Su orts and Han ers l . Integrally Welded Supports 46 46 PT or MT 12 14 20 C-E-1 See Table a 8.4.1-1 Support Components 193 193 VT 50 70 73 C-E-2 R. R~RR Pam a I
- 2. Support Components 16 1 1 C-E-2 a
F. Exem t I Com onents Inspection During Section 8.6 Hydrostatic Testing U 'd Jl H
Cd ad e c lJl C5
TABLE A (UNIT 3)
BROMNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Quantity Inspected . Area 40 Year 10 Year 'ethod 40 80 120 Exam Dose Rate C~om onants ~Sam le S~am le ~of lns t onth Month Heath ~Cate sorar ~4th C ale Remarks A. Reactor Vessel Seam Melds Not In Core Region
- a. Circumferential 28 fta 7 ft. UT 2 ft. 2 fta 3 ft. B-B 10 CHM-2046-C
- b. Longitudinal 23.6 ft. 5.9 ft. UT 1.9 ft. 2 ft. 2 ft. B-B 10 CHM-1095-A
- 2. Closure Head Seam Meld 8 ft. 2 ft. UT .5 ft. .5 ft. 1 ft. B-B 10 CHM"1095-A
- 3. .Closure Head Meridional 24 ft. 6 ft. UT 2 ft. 2 ft. 2 ft. B-B 10 CHM-1095-A Weld 4l Vessel-To-Flange Circumferential Meld 69 fv. 69 ft. UT 23 fte 23 ft. 23 ft. B-C 10 CHM-1095-A i
5'. Head-To-Flange l
Circumferential Meld 66 ft. 66 ft'. UT 22 ft. 22 ft 22 ft. B-C 10 CHM-1095-A
- 6. Primary Nozzles Main Steam (26") CHM-1094-A
- a. Nozzle-To-Vessel 2 B-D 20 Sheet l.
and Inside Radii
- b. Nozzle To-Safe End B-J Core Spray (10") 100 CHM-1094-A
- a. Nozzle-To-Vessel B-D Sheet 1 and Inside Radii
- a. Nozzle-To-Vessel and Inside Radii 6 6 B-D St 1
- b. Nozzle-To-Safe End B-J WVh&
oc w CQ oA~
TABLE A (UNIT 3, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Quantity Inspected Area I 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com onant Samale Samasle o~f lns Month Month Month ~Cate or ~4th C ole Remarks
- 8. Closure Studs 92 92 UT 30 30 32 B-G-1 4 MT 4 B-G-l See Section 6.1.3 Closure Washers and 92 92 30 32 B-G-1 and Bushings 4 4 4 B-G-1 See Section 6.1.3 1 . Ligaments Between 30 30 32 B-G-1 10 Thread Stud Holes I
1 ., CRD Housing Welds 4O 4O Inspection During B-0 50 Request for I
Hydrostatic Tests Relief 1
I ISI-6 I f 12.f'I Vessel Penetrations I. s 63 , 63 Inspection During B-E 20 f
I Hydrostatic Tests 13.
)
Supp/rt Skirt To 4 ft. 4 ft. UT 1 ft. 1 ft. 2 ft.'"H 20 CHM-1091-A Vessel Weld
- 14. Vessel Cladding 6 patches 6 patches VT 2 2 B-I-1 10 15.t Internals General Surveillance B-N-1)B-N-2 10 BF MMI-14.3-A
.I .
B. Pi in Recirculation 20 CHM"2139-C
- a. Circumferential '
8" SS 33 UT B-J 2" SS 10 3 UT B-J 2" SS 40 ... - 10 UT B-J 4" SS 5 1 UT B-J C/1 CX)
TABLE A (UNIT 3, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com oncet R~am le ~Ram la ~of lns Month Month Month Cate~erg ~4th C tie Remarks
- 2. Hain Steam 30 CHM-2140-C
- a. Circumferential Four Welds 26" SS 52 13 4 5 B-J Inaccessible 26" CS (Pipe Whip) 6 6 2 2 B-J (KHS-3-1, 6" CS 50 13 4 4 B-J KMS-3-81,
- b. Branch Pipe KMS-3-29 6 Connection Welds KHS-3"56) 10" CS 1 UT 1 B-J 6" CS 25 PT,MT 2 > 2 B-J 3n CS 1 PT,HT 1 B-J
- a. Circumferential a Two Welds 24" CS 25 6. 2 '-.'
2 B-J Inaccessible 20" CS 6 2 1 B>>J (KFW-3-4, 12" CS 32 8 2 3 3 B-J KFW-3-22) 12" CS (Pipe Whip) 10 10 3 3 4 B-J See Request for Relief ISI-8 (GFW-3-i GFW-3-24)
See Table C
- b. Branch Pipe
' Connection Welds I
l I
I I
TABLE A (UNIT 3, CONTINUED)
BROVNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com onent Saaa)e ~Sam le ~of lns Month Month Month ~Cate or ~4th C ele Remarks l
- 4. Co're Spray 75 CHM-2142-C
- a. Circumferential
! 12" SS 11 3 UT B-J 12" CS 2 UT B-J 12" Dissimilar 6 6. UT, PT B-F 12" CS (Pipe Vhip) 4 4 UT B-J See Table C 10u SS 2 1 UT B-J 10" Dissimilar 2 2 UT, PT B-F 10" CS 4 1 UT B-J RHR 30 CHM-2141-C One Veld
- a. Circumferential Inaccessible 24" SS 21 5 UT B-J (TRHR-3"193) 24" SS (Pipe Vhip) 3 3 UT B-J See Table C 20" SS 7 I 2 UT B-J 20" Dissimilar 1 1 UT, PT B"F 20" CS 2 1 UT B-J 6" SS 24 6 UT ~ B-J 6" Dissimilar 1 1 UT, PT B-F 6" CS 4 1 UT B-J
- b. Branch Pipe Connection Weld B-J
- 6. CRD Hydraulic Return 20 CHM-2143-C a ~ Circumferential
pV c c A ot CC)
CQ a ~ ~
TABLE A (UNIT 3, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS
~
Es timated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate
~Com oncet ~Sam le Samale a~flea Month Month Month ~Cate ~o ~4th C cle Remarks
- 7. RWCU 20-300 CHM-2144-C a.'ircumferential 8" CS 2 B-J 6" SS 11 B-J 6" SS (Pipe Whip) 4 B-J See Table C 4" CS 5 B-J
- 8. RCIC 20 CHM-2144-C
~
4 B-J See Table C
- 10. Pressure Retaining Bolting ll. Pipe and Valve 30-250 Supports and Hangers I a. Integrally Welded 100 25 MT or PT 8 B"K-1 Request for 2 1 UT 1 B-K-1 Relief I
ISI-9 KR-1-54 and KR-1-55 I
- b. Support Components 121 121 35 40 46 B-K-2 Integrally Welded I
Hangers sr~eluded
~ WCnfSS H 4 m c oa oa v)
~ CG
TABLE A (UNIT 3, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS Estimated Quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate C~om onent S~am le ~Sam le o~ff ns Honth Month Month ~Cate ot 4~th C ele Remarks C. Recirculation Pum s 30 Pressure Retaining 32 32 VT, UT,HT 10 10 12 B-G-1 1.
Studs When Removed Nuts 32 32 VT 10 - 10 12 - B-G-l 4
I Ligaments Between 32 32 When Connection is B-G-1 Threaded Stud Holes Disassembled i B-K-1 Integrally Welded UT B-K-1 Supports- VT I.. Pump'Casing During Normal B-L-2 Request for Ma'ntenance Relief I
ISI-4 i
, j I I D Valves I a
i l.~ Valve Bodies 60 During Normal B-M-2 Request for I Maintenance Relief s
I ISI-5
'l I
20 20 20 B-G-2
- 2. Pressure Retaining 60 60 Bolting Inspection During B-P See E. Exam t C m onents VT Hydrostatic Testing Section 6.7
TABLE B (UNIT 3)
BROWNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS Estimated quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate C~om onent ~Sam le ~8am le ~ot lns Month heath Month ~Cate or 4~th C ele Remarks A. RHR Heat Exchan ers
.5 .5 ft -UT .5 ft C-A Bottom Head Flg. Weld (RHRG-11)
Supports 41 B. Main Steam Pi in 20 CHM-2690-C
'1. Circumferential Welds 26" CS 2 1 C-F-24" CS 18 5 2 C-F 18" CS 10 2 1' C-F 6" CS 28 7 C-F I2. Branch Pipe Connection Weld 6" CS C-F Cn P1 0 Mg Mt'5 g ~rg o o A
CO
TABLE B (UNIT 3, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS Quantity Inspected Area 40 Year 10 Year Method 40 80 120 Exam Dose Rate s
~Com onent Sample Sanale ~of lns 11onth Nonth 11onth Categoar ~4th C ele Remarks C. R~RR Pi in 5-40 il. Circumferential Welds 241'CS 40 10 3 3 4 C-F 20"CS 53 14 5 5 4 C-F 18"CS 20 6 2 2 2 C-F 16'ICS 14"CS ll 3 2
1 1 1 C-F C-F 9 1 1 12"CS 1 1 1 C-F 10"CS 10 3 1 1 1 C-F 6"CS 18 5 2. 1 2 C-F in and Valve Su orts and Han ers a 1 I
Integrally Welded Supp'orts 46 46 PT or MT 12 14 20 .
C-E-1 See Table 8.4.1-1
- 2. Support Components 193 193 50 70 73. C-E-2 I
R. R~RR Pnm s
~
I 1
I Integrally Welded Supports PT or MT C-E-l I
I Supp'ort Components 16 4 1 1 C-E-2 I
F. Ex em t Com onents Inspection During Section 8.6 Hydrostatic Testing Wcn~
Q) H Q QCI e wm o a o) ~
A CO
TABLE C MELD INSPECTION FOR PIPE WHIP PROTECTION
~)stem Weld Identification" Hain Steam GHS 32) GHS 15 ) GMS 24) GHS 6) KHS 104) KMS 24 Unit 1, 2, & 3 FeedMater Units 1, 2, 8 3 KFW-39) GFW"15) KFW-38) GFW-9, GFW-12) KFM-13) GFW"26) KFM-31) GFW"29) GFW-32 Unit 1 DSRHR-SA, DSRHR-7) DSRHR-4 Unit 2 DSRHR-4) DSRHR-6) DSRHR-7 Unit 3 DSRHR-4) DSRHR-6) DSRHR-7 Core Spray Unit 1 DSCS-12, DSCS-4, DSCS-ll, DSCS-5
'nits2 8 3 TSCS-407) TSCS-408, TCS-423) TSCS-424 RWCU Units 1, 2, 8 3 DSPMC-4) DSRMC-6, DSRMC-3, DSRMC-5 HPCI Unit 1 THPCI 154) THPCI 152) THPCI 153) THPCI 153B Units 2 Sr 3 THPCI-72, THPCI-70, THPCI-71, THPCI-70A fT]
Q st)CA W Ol H e wm n
CO
BFNP SI 4.6.G Page 70 SEP 2> tSst List of Drawin s Unit 1 Reactor Vessel Drawin No. Title ~Pa e Na.
CHM-992-C Development of Biological Shield and Reactor Vessel Seam Welds CHM-1077-A Reactor Vessel Seam Welds CHM-1090-A Control Rod Drive Penetration (Detail)
CHM-1091-A Support Skirt Weld CHM-1094-A ~ Nozzle to Vessel Welds .
CHM<<1095-A Vessel and Head Welds 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 and Valve Weld Ma s 30A616-1 Weld End Detail - Machined Backing Rings 30A616-4 Weld End Detail CHM-1080-C Feedwater System Code Class 1 CHM-1081-C Recirculation System - Code Class 1 CHM-1082-C Mainsteam 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 Clean-up and RCIC.--
Code Class 1 CHM-1099-C High Pressure Coolant Injection - Code Class 1 CHM-2676-C RHR Shutdown Sypply Code Class 2 CHM-2690-C Main Steam System Code Class 2 Pi in and Valve Han er Ma s CHM-2036-C Feedwater System Code Class 1 CHM-2037-'C Recirculation System Code Class CHM-2038-C Mainsteam System Code Class 1 CHM-2039-C RHR System 'ode Class 1 CHM-2040-C Core Spray System Code Class 1 CHM-2042-C Reactor Water Clean-up and RCIC-Code Class 1 "CHN-'2043-C' 'igh Pressur'e 'CooIant In]ection Code Class 1
~ IAIIVO 5 CA 40 I
COVRSE 0 N3 N3A N3D iN3C I ~
I V'5 A v s'4 44 I I 204 I44'C COVRSC LL 4A I ~ ~
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~
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BRON( N S FERRY NUCLEAR PLANT REACTOR VESSEL BEAM WE LOS
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NOZZLE NOZZ LE TO VESSEL WELDS BROVVNS FERRY NUCLEAR PLANT CHMlOmi Pry
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cO TVA IDENTIFICATION
,0 B'W IDENTIFICATION 59 ROW I QQQQQQQ 55 ROW 3 QQQQQQOQQ NOZZLES APE SPECIFIED 51 ROW 5 QQQQQ QQ QQ Q Q BT X Y COORDINATES 47 ROW 7 QQQQQQQQQQQ QQ 43 ROW 9 QQQQQQQQQQQQ QQQ 39 ROW II QQOQQQQQQQQQ QQ,G EXAMPLE: PENETRATION NUMBER 5835 OR X IS 35 ROW I3 QQQQQQQQQQQQ QQ I 3I ROW 15 QQQQQQQQQQQQ QQQ 27 ROW I 7 QQQQQQQQQQQQ QQQ 23 ROW I9 QQQQQQQQQQQQ QQQ I9 ROW 2I QQQQQQQQQQQQ QQQ t5 ROW 23 QQQQQQQQQQQ QQ I I ROW 25 QQQQQQQQQQ O ASSUMED NORTH LOONNC DOWN ON VESSEL 07 ROW 27 QQQQQQQQQ I 03 ROW 28 QQQQQQQ 7CNVC'%$Ct VAl.lCY JVIHOklTY
~ 't'lO Ot ~ ~~ ~PC+
CON IROI RM DRIVt; REACTOR VFSSE'ENE TRAT IONS 0;VNS FE+QY 4 'CLEAR PLAN T
':Cg P
04 I
Y" DIMENSIONS Q NGA - 6%e"
~oo ~ N6B - 65/e" C4 W Cl 00 N7 - 97/ts Ctr 4Q M
V) C4 QJ
~RCH X-IV BIRCH-X-6V RCH-X-2Vg I N6ABC-X-I Q
RGH"X"lG H6A N6BBC-X" N7BG-X-3 27P' ON7 904 N6A X-I RCH-X-3V N68-X-I~
NT-X-I RCH-X-5V RCH-X~
BIRCH-X-4V
~
I l804 TENNESSEE YA11EY AUTHORITY NOTES'.
I. ENLACE THE X IN THE WELD NUMBERS BROWNS FERRY NUCLEAR PLANT WITH THE APPROPRIATE UNIT NUMBER..
UN)TS I"3 CLOSURE HEAD ASSEMBQ SELD LOGATlONS AttlggO
-+M --- CH-M-21 -A
BFNP SX 4.6.C FLANGE SEAL SURFACE Page 90 89 198t
'll NO. I dl NO. 2 NQ, 5" NO. 4 dl
'lI NO. 5 NO. 6 N4A NOD .
FEEDWATER .FEEDWATER NOZZLE NOZZLE I
2IOo TENNESSEE VALLEY ALITKORITY D)VISION OS NIICLEAR ItONfR EROWNS FERRY NUCLEAR PLANT UNiTS I" 3 REACTOR VESSEL CLAD PATCHES SC1LO SVWAITTlD OAtt OOAWN W MW tH!tt Ot tHtttt lRACtD MSG CHtCKtD
RHRG RHRG RHRG RHRG-l0-L e RHRG NOTEc PLACE HEAT EXCHANGER NUMBER AT THE OF THE WELD NUMBER RHRG lNOZZLE BrDE) 5-2V.SI RDO A01E NOo RHRG l4 SECTION 'A-A' SECTION
'8-8'ROGANS FERRY NUCLEAR PLANT WlTS l-3 RHR HEAT EXCHANGER WELOS fit ~ .~ q i
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kohen acfua/ /Dis /ess than A= nominal oufside dienwter nominal /eave parent me/al 8= nom/Ina/ inst+'e di'ametef be~nd machined surfeces C=/narahi ned inside di'amef er undisPurbe'd.
f = nom/Intel wall fbi ckness iVcrk 7 0 s'caler NKI DING SPECIFICATION T YPICP I CF PIP'lNC MECHANICAL BROWNS FERRY NUCLEAR WELD END DETAIL Wt alt P'I: AN T MACHINED BACKING RINGS sar, GEHERAI
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IEES xga DATE I R I'4IO GFW rveKSMI <<klllr I 8R rtEYISCNS A~>>rr a>><<0<<a IVae ae <<O<<>>
SROeNoS FERRY IPJCLEAR PL$ 7IT I'NIT < ~S81 FEEDWATER SYSTEM BROWNS FERRY NUCLEAR PLANT DPP Assigned Weld No. Size Material GFW-l-l 24 II A106 GrB E
KFW-l-l 241l A106 GrB KFM-1"3 1 6 II A106 GrB GFW-1" 2 24tl A106 GrB GFM-1-4 24" A106 GrB KFM-1-4 24 II A106 GrB KFW-1"5 24" A106 GrB GFW-1"5 24ll A106 GrB KFM-1-6 240 l A106 GrB KFW 1-7 24" A106 GrB KFM-1"8 24lt A106 GrB GFM-1-6 24)I A106 GrB GFW-1-7 24" A106 GrB KFM"1"9 24" A106 GrB KFW-1-10 20'> A106 GrB KFW-1-11 20 1l A106 GrB KFW-1-12 20tt A106 GrB GFW-1-8 12tt A106 GrB GFW"1-8A 12lt Meld Repair KFW-1-13 12lt A106 GrB GFW-1-9 12tt A106 GrB GFM"1"lp ] 2lt A106 GrB KFV"1"14 12" A106 GrB KFW-1"15 ] 2tt A106 GrB
BFNP SI 4.6.G Page 96 SEP 23 198]
FEEDWATER SYSTEM BROWNS FERRY NUCLEAR PLANT Continued DPP Assigned Weld No. Size Material GFW"1"ll ] 2lt A106 GrB GFW-1-12 ] 2II A106 GrB GFW-1-13 12tl A106 GrB KFW-1-16 12tt A106 GrB KFW-1-17 12" A106 GrB GFW-1-14 12" A106 GrB GFW-1-15 12II A106 GrB GFW"1-16 12" A106 GrB KFW"1-18 12lt A106 GrB KFW"1-19 A106 GrB 12I'4tl GFW-1"17 A106 GrB GFW-1"18 A106 GrB KFW>>1-21 8lt A106 GrB GFW-1"19 24" A106 GrB GFW-1-20 24I I A106 GrB r
GFW-1-21 24tl A106 GrB KFW-1-22 24ll A106 GrB KFW-1"23 24 II A106 GrB GFW<<1-22 24 I I A106 GrB KFW-1"24 24" A106 GrB KFW-1-25 24ll A106 GrB KFW-1"26 24I I A106 GrB GFW-1-23 24I I A106 GrB GFW-1-24 24tt A106'rB
BFNP SI 4~ 6.G Page 97 SEI 2d 198]
FEEDWATER SYSTEM BROWNS FERRY NUCLEAR PLANT Continued DPP Assigned Weld No. Size Material KFW-1-27 24I t A106 GrB KFW-1-28 2P tt A106 GrB KFW-1"29 20 1l A106 GrB KFW-1-30 2Ptt A106 GrB GFW"1"25 12 II A106 GrB KFW-1-31 12" A106 GrB GFW<<l"26 ] 2lt A106 GrB GFW-1"27 12" A106 GrB KFW-1-32 12tl A106 GrB KFW-1-33 12" A106 GrB GFW-1-28 12ll A106 GrB GFW-1-29 ] 2lt A106 GrB GFW-1>>30 ] 2ll A106 GrB KFW-1-34 12" A106 GrB KFW-1-35 A106 GrB GFW-1-31 ] 2II A106 GrB GFW-1>>32 12" A106 GrB GFW-1-33 12" A106 GrB KFW>>1-36 12tl A106 GrB KFW-1-37 1 2 II A106 GrB GFW-1-34 12lt A106 GrB KFW"1-38 ] 2lt A106 GrB KFW-1-39 ]2 II A106 GrB
Mtb I ST NZE l50 820 IZO SIC 9(P HZ 8 60>> 30'IA ttZA NZK 0>> ZTO'ZC NZN
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&I6 KR1r50 OR I 54 GRt5 GR1%I GR I M CONTINUED Pl I
Q>> AT POINT A FCY 68 33 KG&19 CR I I5 OR Ir9 GR I GR I >>8 GR t4I GRAS .I46 ) CR I I2 KR I g KRIS KR I KR1 42 r jkk FCY 68 3S 20 ~KR-I-l9 f81 ll KR I15 Kf l14 EL. 580 9 ~
I I'34 CR-I ZS 'CRII-IS- KR112 KR I'Is KR I 37 KR ~GR I 44 1 q PONT A i I OR+34~ I
~ 7 GR 1.8 IXWTINUD)FROM PONT S l088 I i KR I 25 CONTRIVED FROM KR CN M I-3 C
CH M ON-C k pGR-I-33 KR I4 r
CR I-2 KR IZS -I 7 GR I'2R t I RBC DECONTAIANATIOM I.Z GR1 j27
. 'CY68 CR OH + FCYCB I.2 KR PVNP I IS E~6'~ PUMP I IA KR I 5I~ FCV68 77
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<CR-I-63A Y.r PI tOACR o 4 DECONTANTIATON RBC I'tt 5 Ir tB l"U>>gr i~>>C>jqctv.v RKlnyCNS 3RENOVE RECON PUMP OUTLET VALVES R~W~
Z.NLETED GR I 65 8 GR I C6 TRAYS fERED KR I 54 S KR I >>'3 0 DWCr GE ISSFTS4 Ctt M 2037 C.
KELLOGG SF21SO I.ADDED WELDS CR-I 634 AND CR I-638 K
l KELLOGG QIOP WELD G>> CE FIELD WELD "r~
XR N M REOACVLATION UNIT tKL WELD I
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Tth~ttttt V>>litt AUTHO>>at Olrl1A>>r Art~ >>tOpr(%I BROWN 9 FERRY hVCLEAR PLANT UVT I
'+ELD tCEN >FIC>TICN RECIRCVLATICtt SYSTEM C r <<>>~H NNYNC>>t ~ C>>.
BFNP SI 4.6.G Page 99 RECIRCULATION SYSTEM SEP 28 )98'I BROWNS PERRY NUCLEAR PLANT DPP Assigned Weld No. Size Material GR-l-l 28" W/Seam
'358 GR"1"2 28tt A358 W/Seam KR-l-l 4 II A376 304 GR-1-3 28" A358 W/Seam KR-1-2 28 I I A358 W/Seam KR-1"3 28 ll A358 W/Seam KR-1-4 4tl A376 304 GR-1-4 4ll A376 304 GR-1-7 4tl A376 304 GR-1"8 28tl A358 W/Seam KR-l-ll 28 I I A358 W/Seam KR-1-12 22" A358 W/Seam KR"1"13 A403 KR-1"14 121I+ A403 KR-1-15 22" A358 W/Seam GR-1"9 l 2's A358 W/Seam GR-1-10 12" A358 W/Seam KR-1"16 12" A358 W/Seam GR-1"11 12" A358 W/Seam GR-l-l2 A358 W/Seam GR-1"13 12 A358 W/Seam KR-1-17 12tl A358 W/Seam GR-1-14 12" A358 W/Seam GR-1-15 ] 2tl A358 W/Seam
BFNP SI 4.6.G Page 100 SEP P,g ]gg]
RECIRCULATION SYSTEM BROWNS PERRY NUCLEAR PLANT Continued DPP Assigned Weld No. Size Material GR-1-16 1 2ll A358 W/Seam KR-1-18 A358 W/Seam GR-1-17 12" A358 W/Seam GR"1-18 22" A358 W/Seam KR-1-19 12"+ A403 KR-1-20 ] 2ll+ A403 GR-1-19 12ll A358 W/Seam GR"1-20 12lt A358 W/Seam KR-1-21 ] 2lt A358 W/Seam GR-1-21 12" A358 W/Seam GR-1-22 12" A358 W/Seam GR-1-23 12lf A358 W/Seam KR-1-22 1 2I I A358 W/Seam GR-1"24 12" A358 W/Seam GR-1-25 221l A358 W/Seam GR-1>>26 22 II A358 W/Seam GR-1-27 28 II A358 W/Seam GR"1"28 28" A348 W/Seam KR-1-23 4ll A376 304" GR"1"29 28" A358 W/Seam KR-1-24 A358 W/Seam KR-1-25 28 I 1
...A358 W/Seam...
4II KR-1-26 GR"1"30
- -- 4n A376 304 A376 304
BPNP ST. 4.6.G Page 101 SEP SS >Ss>
RECIRCULATION SYSTEM BROWNS FERRY NUCLEAR PLANT Continued DPP Assigned Weld No. Size Material GR-1-33 4tl A376 304 GR-1"34 28 A358 W/Seam KR-1"33 28" A358 W/Seam KR"1-34 22tl A358 W/Seam KR-1"35 12"+ A403 KR-1-36 1 2 I I+ A403 KR-1"37 22lt A358 W/Seam GR"1"35 1 2 II A358 W/Seam GR-1-36 12" A358 W/Seam KR-1-38 12" A358 W/Seam GR"1"37 ]2" A358 W/Seam GR"1"38 12" A358 W/Seam GR-1-39 ]2" A358 W/Seam KR-1-39 ] 2tt A358 W/Seam GR-1-40 12 A358 W/Seam GR-1-41 12 II A358 W/Seam GR-1"42 ] 2ll A358 W/Seam KR-1-40 12fl A358 W/Seam GR-1-43 12" A358 W/Seam GR-1-44 $ 2lt A358 W/Seam KR-1-41 A403 KR-1"42 12tl+ A403 L
GR-1-45 12" A358 W/Seam GR-1-46 12tt A358 W/Seam
BFHP SI 4.6.G Page 102 SEP 29 198)
REC1RCULATroN SYSTEM BROWNS FERRY NUCLEAR PLANT Continued DPP Assigned Weld No. Size Material KR-1-43 12" A358 W/Seam GR"1-47 12" A358 W/Seam GR-1-48 12" A358 W/Seam GR-1-49 1 2ll A358 W/Seam KR-1-44 12tl A358 W/Seam GR"1-50 12'I A358 W/Seam GR-1"51 22 II A358 W/Seam GR-1-52 22l I A358 W/Seam GR-1-53 28" A358 W/Seam KR-1-45 28" A358 W/Seam GR"1-54 28" A358 W/Seam GR-1"55 2glt A358 W/Seam KR-1-46 2 8 II A358 W/Seam KR-1-47 2gll A358 W/Seam GR-1-56 28" A358 W/Seam GR"1-57 28 II A358 W/Seam GR"1-58 2glt A358 W/Seam KR"1-48 28" A358 W/Seam KR-1-49 4II A358 W/Seam GR-1-59 28' A358 W/Seam KR-1-50 A358 W/Seam GR-1-60 8 II .A358 W/Seam GR"1-61 A358 W/Seam KR-1-51 2gll A358 W/Seam
BFNP
, SI 4.6.G Page 103 SEP 29 'l98l RECIRCULATION SYSTEM BROWNS FERRY NUCLEAR PLANT Continued DPP Assigned Weld No. Size Material GR-1-62 28" A358 W/Seam GR-1-63 A358 W/Seam GR-1-63A 4u A358 GR-1-63B 4II A358 KR-1-52 28lt A358 W/Seam KR-1-53 4lt GR-1-64 28" A358 W/Seam Reference Drawings:
TVA 47K1544-1 GE 153F754 Kellogg BF2-180
KMS 1-22 KMS I 21 CD KMS.I- 20 CD N3A N30
~
uw~ O 72>> 288 CR7 KMS.I ~
19 KMS.I 103 I KM5- I'18 M ,KMS. I. IO 2 cn o QJ KMS.IH7 KMS I-IOI CQ KMS-I 16 I
'MS-I.
KMS-I 100 KM5-1-15 8 GM 5.1.34 KMS.I. 99 KMS-1-14 KMS-I.28 KMS 108 KMS-1-98 KMS-1-97 K MS.I. I 3 5 KM5.1.27 K MS-I- 107 KMS- I- 96 KMS-I. 12 KMS-1-95 KMS- I-I I GMS-I- 33 KM5 1-94 KM5-I-93 GMS.I. 7 KMS 1-92 KM5-I IO KM5 1-91 KM5.1-9 KMS-I. 90 KM 5-1-8 KM5.1-89 .
KMS-1.88 I KMS.I- 7 KM5-1-87 I KMS-1-6 KMS- I- 86 I KMS-IB KMS-I 85 I
l KMS-I- 5 KM5.1-84 l KMS-I 4 KMS I 83 KMS-1-3 I
LINE A EL 586 7 LINE D MS-1-6 CMS.1 32 KMS-1-2 5 KMS-1-24 KMS I 105 17 KMS-It2 KMS>> I IO4 KMS.I.82 KMS 1-26 KMS-I IO GMS-1-5 16
~S I" CMS.I. 31 II Ill GMS-1-4 Itlll CMS-1-30 KM51 1 GMS-1-3 REF. DWGS. CMS I 27 G MS-I.I TVA 47 K1767 KM5-1.81 REVISION I NOTES:, gttl>>
GMS-1-2 TVA 47W335-I CM5.1.29 DELETED WELOS GMS-I 3$
KELLOCG 729E229 ANO Clg I 4I ~
CvS-I 28 Q INDI CAT E5 P IECE NUM BER tt>>NttStt YALLCY AUTHO>>llY 0>>I>>t>> tt ttttt ttttlJtkl0>>
VNIT NO. WELD I DENTIFI CAT ION K ~ KELLOGG SHOP 'WELD WEI.D NO. REACTOR MAIN STEAM SYSTEM G-CE FIE'LD WELD BROWN5 FERRY NVCLFAR PLANT H M IO~
CO CPi
.oI I III Cra DI
~ KMS. I 6 6 N3C 252o KMS 1-6 5 CMS 1.17 KM5 1-64 GMS 126 KMS-I.55 KMS 1.69 KM5-I 80 KMS-1-68 KMS'-1-67 KMS-I~ 72 10 KMS-1-71 15 KM5-I 54 KM5- 1-70 KMS 1-79 GMS-I.I 5 KM5-1-75 K MS-1-74 GMS-I- 25 KM5-1.37 CMS 1-16 KM5-I 73 KMS. 1-36 KM5 I 78 KM 5-1-35 14 ~
~
KMS.I.42 KMS 177 GMS 24 KM5-1-34 KM5 I 41 K MS- I -33 KM5 I 40 KM5-I 59 KMS 132 KMS-I-4 5 KMS!48 13 KMS-I 60 KM5 !44 K+53.47 KM5-I - 61 KM5>50 KMS 1-58 LINE 8 EL 555'" KMS I 49 LFNE C KM5-I.31 MS-I 14 KM5-1-53 KM5-I-?6 I2 31 CM5-1-13 KM5-1-38 KMS-I. 52 G M5. 1-2 3 GIN'S 122 IO HP!C
! I Ill GMS-I.I2 CMS 1.21 EL 568 I
! IIII KM5.1- 30 KM5 I- 63 KMS I'57 KM5. 1-29 3" RCIC KMS I 56 CMS - I- II GMS-I 20 GM5-1-18 M5- I-IO REF. OWGS.
CMS.I- 19 GMS-1-9 TVA 47K 1767 TVA 47W335-I IIEYISIOH I IIOTESI IITIiII KELLOGG 729E229 DELETED WELDS GMS I 37 AND GrAS I-39.
Q INDICA'TES PIECE NUMBER
'Ttl5IICSStt VALLtT AVT55OAITT Osnlaa 55 ATNII ~ 555NEININ KT KELLOGG 5HOP WELD MAIN 5T EAM WELD NO. WELD IDENT IF ICATION CAGE FIELD WELD REACTOR MAIN STEAM 5YSTEM 8ROWNS FERRY NUCLEAR PLANT
<<5 TI ~ ea ~ ~
M'82+
BFNP SI 4.6.G Page 106 SEP 2S MAIN STEAM SYSTEM
~98'PP BROWNS FERRY NUCLEAR PIANT Assigned Weld No. Size Material GMS"1-1 26II A155 KC70 GMS"1-2 A155 KC70 GMS-1-3 26lt A155 KC70 KMS-l-l 26" A155 KC70 GMS-1"4 26" A155 KC70 GMS-1-5 26" A155 KC70 KMS-1-2 26 II A155 KC70 KMS-1-3 6 I I+ C.S; KMS-1-4 61I, C.S.
KMS-1-5 6 II C.S.
KMS"1"6 6tt+ C.S.
KMS-1-7 6ll C.S.
KMS"1-8 6 II C.S.
KMS"1"9 6 I I+ C.S.
KMS-1-10 6lt C.S.
KMS-.1"11 C.S.
KMS"l"12 6tl+ C.S.
KMS-1-13 6ll C.S.
KMS-1-14 6lt C.S.
KMS-1-15 6tt+ C.S.
KMS-1-16 6ll C.S.
KMS-1"17 6 ll C.S.
KMS-l-lS 6 I I+ C.S.
KMS"1-19
'- --6n - C:S.
81'NP SE 4.6.G Page 107 MAIN STEAM SYSTEM BROWNS FERRY NUCLEAR PLANT Continued)
DPP Assigned Weld No. Size Material KMS-1-20 6II C.S.
KMS-1-21 6 II C.S.
KMS"1-22 6 II C.S.
KMS-1-23 6ll C.S..
KMS-1-24 A155 KC70 KMS-1-25 A155 KC70 KMS-1-26 26" A155 KC70 J
GMS"1-6 A155 KC70 GMS"1-7 26 I I A155 KC70 KMS"1-27 26" A155 KC70 KMS-1-28 26 I I A155 KC70 GMS-1-8 261I A155 KC70 GMS-1"9 26tl A155 KC70 GMS"1-10 26" A155 KC70 GMS"1"11 26" A155 KC70 KMS"1-29 26 I I A155 KC70 KMS-1-30 26" A155 KC70 GMS-1-12 26 I l A155 KC70 GMS-1-13 A155 KC70 KMS-1-31 26lt A155 KC70 KMS"1-32 6 I I+ C.S.
KMS-1-33 6 II C.S.
KMS-1"34 6 II C.S.
KMS-1-35 6 It+ C.S.
BFNP SZ 4.6.G Page 108 SEP 29 881 MAIN STEAM SYSTEM BROWNS FERRY NUCLEAR PLANT Continued DPP Assigned Weld No. Size Material KMS-1-36 6 II C.S.
KMS-1-37 6lt C.S.
KMS-1-"38 A155 KC70 GMS-1-14 26tt A155 KC70 KMS-1"40 6 lt+ C.S.
KMS>>l-41 6lt C.S.
KMS-1<<42 6 II C.S.
KMS-1-43 6ll+ C.S.
KMS-1-44 6tt C.S.
KMS-1-45 6ll C.S.
KMS"1-46 6 I I+ C.S.
KMS-1-47 6lt C.S.
KMS-1-48 6tl C.S.
KMS-1-49 6tt+ C.S.
KMS-1-50 6tl C.S.
KMS-1-51 6lt C.S.
KHS-1-52 26tl A155 KC70 KMS-1-53 C.S.
GMS-1-15 A155 KC70 GMS-1-16 26 A155 KC70 KMS-1-54 26" A155. KC70 KMS-1-55 A155,KC70 GMS-1-17 26ft A155 KC70 GMS"1-18 Z6" A155'C70
'(+'%
I
BFNP SI 4.6.G Page 109 SEP S> >981 MAIN STEAM SYSTEM BROWNS FERRY NUCLEAR PLANT Continued DPP Assigned Meld No. Size Material GMS"1"19 A155 KC70 GMS"1"20 26" A155 KC70 KMS-1"56 A155 KC70 KMS-1>>57 6tl A155 KC70 GMS-1>>21 26tt A155 KC70 GMS-1-22 2611 A155 KC70 KMS"1-58 A155 KC70 KMS"1-59 6tl C.S.
KMS-1-60 6lt C.S.
KMS-1-61 611+ C.S.
ZMS-1-62 A155 KC70 KMS-1-63 3 1 1+ C.S.
GMS-1-23 A155 KC70 KMS-1-64 C.S.
,KMS"1-65 r
611 C.S.
KMS-1-66 6tl C.S.
KMS-1"67 6 I 1+ C.S.
KMS"1-68 611 C.S.
KMS-1"69 6tt C.S.
KMS-1"70 6tl+ C.S.
KMS-1-71 611 C.S.
KMS-1-72 6" C.S.
KMS-1-73 611+ C.S.
KMS"1-74 6tt C.S.
\
'I
\"
BPNP ST. 4.6.0 Page 110 SEF'23 198'l MAIN STEAM SYSTEM BROWNS FERRY NUCLEAR PLANT Continued DPP Assigned Weld No. Size Material KMS-1-75 6tt C.S.
KMS-1-76 26t I A155 KC70 GMS-1"24 26 I l A155 KC70 KMS-1-77 26" A155 KC70 KMS-1-78 26tl A155 KC70 GMS-1-25 26 I I A155 KC70 KMS"1-79 A155 KC70 "KMS-1-80 26tt A155 KC70 GMS"1"26 26" A155 KC70 GMS"1-27 26tt A155 KC70 GMS-1-28 26tt A155 KC70 GMS-1-29 A155 KC70 KMS"1"81 A155 KC70 GMS"1"30 26" A155 KC70 GMS-1"31 2gt A155 KC70 IQfS-1-82 26 ll A155 KC70 KMS-1-83 6 II+ C.S.
KMS-1-84 6tt C.S.
KMS"1"85 6tt C.S.
KMS-1"86 6tt+ C.S.
KMS-1-87 6ll C.S.
KMS-1-88 C.S.
KMS-1-89 6tl+ C.S.
KMS-1-90 6tt C.S.
BFNP Sl 4.6.G Page ill MAIN STEAM SYSTEM SEPZP ~gg~
BROWNS. FERRY NUCLEAR PLANT Continued DPP Assigned Veld No. Size Material KMS-1-91 6tl C.S.
KMS-1-92 6 It+ C.S.
KMS-1-93 6lt C.S.
KMS-1-94 6lt C.S.
KMS-1-95 6l I+ C.S.
ZMS-1"96 6ll C.S.
KMS-1-97 6tl C.S.
KMS-1>>98 6t t+ C.S.
KMS"1-99 6ll C.S.
KMS"1"100 6ll C.S.
KMS-1"101 6 ll+ C.S.
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BPNP SI 4.6.G Page 115
~~I'29 1981 RHR SYSTEM BROWNS FERRY NUCLEAR PLANT DPP Assigned Weld No. Size Material DRHR" 24tl SS 1-3'RHR-1" 3B 24" SS DRHR-1-4 24ll SS DSRHR-1-1 24tl SS DSRHR" 1-2 24 II SS DRHR-1-5 241 t SS DRHR-1-6 24" SS DSRHR" 1-3 24tt SS DSRHR"l-4 24tl SS DSRHR" 1-4A 24" SS DRHR-1-7 24tl SS DRHR-1-8 24lt SS DRHR-1-9 24" SS DRHR-1" 12 24lt SS DRHR-1-13 24" SS DSRHR-1" 5 24tl SS DSRHR" 1-5A 24tl SS DRHR<<l-14 24" SS DRHR-1-15 24" SS DSRHR" 1" 6 24" SS DSRHR-1-7 24tl SS DSRHR" 1-8A 24" SS 9SRHR-1-8B 24ll SS DRHR-1-16 24" SS
BFNP SI 4.6.G Page 116 RHR SYSTEH SEI'20 1981 BROVNS FERRY NUCLEAR PLANT Continued DPP Assigned Veld No. Size Material DRHR" 1-17 24" SS DRHR-1" 18 24" SS DRHR-1-19 20tt SS DSRHR-1-8 DSRHR=1" 9 2Ptt DRHR-1-20 20" SS DRHR-1-21 20tt SS DSRHR-1-10 2PII SS DSRHR-l-ll 20tt" SS DRHR-1 "22 20tt SS A
TRHR-1" 190 20" CS 5 TRHR-1-191 20" CS TRHR" 1" 192 20 II CS TRHR-I-1.94 20I' CS DHS-1-1 SS DSHS"1"1 SS DSHS-1"1A II SS DSHS-1-1A 6tf SS DSHS-1-2 6lt SS DSHS-1-3 6tl SS DSHS-1-4 6tl SS DSHS-1-5 6ll DHS-1-2 61t SS DSHS-1-6 SS
BFiH'I 4.6.6 Page 117 SEP 29 i981 RHR SYSTEM BROWNS PERRY NUCLEAR PLANT Continued DPP Assigned Veld No. Size Materi a1 DSHS-1"7 6tt SS DSHS-1-8 6tl SS DHS"1-3 6tt SS DSHS-1"9 6tt SS DSHS-1-10 6ll SS DSHS-1-11 6tt SS DSHS"l-l2 6lt SS DSHS-1-13 6tl SS DSHS-1-14 6tt SS DSHS"1-15 6tl SS DHS-1-4 6 II SS DHS-1-5 6lt SS DSHS-1-16 6 It SS DSHS"1-17 6lt SS DSHS-1-18 SS DSHS"1-19 6tt SS DHS-1"6 6lt SS TRHR-1-454G 6tl CS t TRHR"1-454E 6tt cs TRHR-1-454A 6 II cs TEE-1-454D 6lt CS TRHR-1-454F 6tl CS
REFQKNCE ORATANGS 47KI772 47WSSS l5 CO ORAVO E2456 CC 54 CD DRAVO E2456 CC 35 0 oo
~ rl gw e 240'20854 N58 tcr I-I cd CCI M EIc QJ f-OCS l9 h
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0 BFNP ST. 4.6.G Page 119
~~I'29 198]
CORE SPRAY SYSTEM BROWNS FERRY NUCLEAR PLANT DPP Assigned Weld No. Size Material DCS>>1-3 12 SS DCS-1-4 12" . SS DCS-1-4A 12" SS DSCS-1-1 1 2I I SS DSCS-1"2 ] 2ll SS DCS-1-5 12lt SS DCS-1-6 12" SS DSCS-1-3 1 21l SS DSCS-1-4 ] 2ll SS DSCS-1-5 SS DCS-1-7 ] 2II SS DCS-1-8 12II SS DSCS-1-6 10lt SS DCS-1-9 1PII SS DCS-1-12 12" SS DCS"1-12A SS DCS-1-13 12" SS DSCS-1-7 1 2ll SS DSCS-1-8 12" SS DSCS"1-9 ] 2ll SS DCS-1"14 12" SS DCS-1"15 12lt SS DSCS"1"10 ] 2lt SS DSCS-1-11 12tt SS
BFNP SI 4.6eG Page 120 SEE'23 I981 CORE SPRAY SYSTEM BROWNS FERRY NUCLEAR PLANT DPP Assigned Size Weld No. ~Inches Material DSCS-12 12 SS DCS-1-16 12 SS DCS-1-17 12 SS DSCS-1-13 10 SS DCS-1-18 10 SS Reference Drawings:
TVA 47K1772 TVA 47W335-15 DRAVO '2456IC-34 DRAVO E2456IC-35 Note: See unit 2 weld listing for core spray
CO CD C" H
~ Al CD OG Cg co g4 ACRO I-49 85-SETT RCRO-I-48 RCRO I 4S RCROS-I-I k RCRO-I- 4S
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~ neAe W ~0 AOAAA1s5V WELO IOENTIFICATION CRO HYDRAULIC RETURN LINE BROWNS FERRT NUCLEAR PLANT HM.IQ97-C
BFNP S I. 4 e 6. (s Page 122 SE1'29 1981 CONTROL ROD DRIVE HYDRAULIC RETURN BROWNS FERRY NUCLEAR PLANT DPP Assigned Size Weld No. ~(Inches Material RCRDS-l-l CS RCRDS-1-2 CS RCRDS-1-3 CS RCRDS-1-43 CS RCRD-1-44 CS RCRD-1-45 CS RCRD-1-46 CS RCRD-1-47 CS RCRD-1-48 CS RCRD-1-49 CS to SS Reference Drawing:
0 4TW 335.14 4TW335 IT 4TIOTT8 QRAVQ 2456 IC.49 DRAV3 2460 IC~
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BFNP SI 4.6.G Page 124 SEP 29 1981'EACTOR WATER CLEAN-UP AND REACTOR CORE ISOLATION COOLING BROWNS FERRY NUCLEAR PLANT DPP Assigned Size Weld No. ~(Inchee Matex ial DRCW-1-1A SS DRWC-1-1B SS DRWC-1-1 SS DSRWC-1-1 SS DRWC-1-2 SS DRWC-1-3 SS DSRWC-1-1A SS DSRWC-1-2 SS DSRWC-1-3 SS DSRWC-1-4 SS DSRWC-1-5 SS DSRWC-1-6 SS DSRWC-1-7 SS DRWC-1-4 SS DRWC-1-5A SS DRWC-1-5B 6 SS DRWC-1-60 CS DRWC-1-61 CS DSRWC-1-10 CS DSRWC-l-ll CS DRWC-1-9 CS DSRWC-1-8 .4 -- CS-DSRWC-1-9 CS
BFNP SI 4.6.G Page 125 SEP 29 1981 REACTOR WATER CLEAN-UP AND REACTOR CORE ISOLATION COOLING BROWNS FERRY NUCLEAR PLANT DPP Assigned Size Weld No. ~Inches Material TRCIC-1-2 CS TRCIC 3 CS TRCIC-1-4 CS TRCIC-1-5 CS Reference Drawings:
TVA 47W335-17 TVA 47W335-14 TVA 47K1778 DRAVO 2456IC-40 DRAVO 2456IC-49
CO CD 4I R M IIIII0 C AT POINT A fJa H IO EL. 574 5 sam a LLJ CQ pp~-eeac I- I THPCI THPC I-I- 5 r
THPCI-1-14e THPCI I-3
. THPCI l-4 1HPCI:I l49 k TkPCI-I-15IA THFC 1.1-150 THPCI I 151 THPCt t 152. I ~
THPCI- I. 1539 THPCI-I 153A THPC I- I - I 53 THPCI-t 154 THPCI.I- I 5 5 TH PC I I I 57 REFT EIV/GS, THPC I I I 5 TVA 47W335 9 THPCI 1-158 TVA 47W335 II TVA 47 K 1567 .
THPCI-I-I 59 THPCI-N- N
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CNTC HIGH PRESSURE COOLANT INJECT ION TC tHC'O'SCC
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H>A@99 C
BFNP S'I 4.6.G Page 127 HIGH-PRESSURE COOLANT INJECTION SYSTEM SEP 20 1Q81 BROMNS FERRY NUCLEAR PLANT DPP Assigned Size Veld No. ~Inches Maeerial THPC1-1-1 16 CS THPCl-1-3 14 CS THPC1-1-4 14 CS THPCl-1-5 CS THPC1-1-148 lo CS THPC1-1-149 10 CS THPCl-1-150 10 CS THPCl-1-151 10 CS THPC1>>l-151A 10 CS THP C1-1-152 10 CS THPCl-1;153 10 CS THPCl-1-153A 10 CS THPC1-1-153B 10 CS THPCl-1-154 10 THPCl-1-155 10 CS THPCl-1-156 10 CS THPC1-1-157 10 CS THPCl-1-158 10 CS THPC1-1-159 10 CS THPC1-1-160 10 CS Reference Drawings:
TVA 47W335-9 TVA 47W335-11 TVA 47K1567
TRHR. 1-23 4 pPHtt I 235
~HR I 236 TRHR-I-2ll TRI4?.I.ZIO TRHR.I-209 FCV 74 47.~
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TRtttt-I-ZIZ TAIN.I-208 TRHR-1-195 CS
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~
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~ l.270
~
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~ gMATCII Uv F 7 HII I 3II TRIIA-I-261 CROSS ThN?.1-301 7AIR4.260 TIE TRttA.I-MH) AHAB-276 7 RHR4.259 ~WFLINIT 2 TRNA.I.F75 l
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TRNR-I-34 88 O
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- A 2, TRNR-I-579X TRHR-I-400 24 QD.X $ 00 MOM. WALLTHK.,C.S.
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BFNP SI 4.6.G Page 144 SEpsr >ss~
List of Drawin s Unit 2 Reactor Vessel Title ~Pa e No.
CHM-1077-A Reactor Vessel Seam Welds CHM-1090-A Control Rod Drive Penetration (Detail)
CHM-1091-A Support Skirt Weld CHM-)004-A Nozzle to Vessel Weld CHM-1095-A Vessel and Head Welds CHM<<2001-C Vessel Stud Locations CHM-2002-C Control Rod Drive Penetrations (Locations)
CHM-2046-C Development of Biological Shield and Reactor Vessel Seam Welds CHM-2102-A Closure Head Assembly MSG-0020-A Reactor Vessel Clad Patches Residual Heat Removal Heat Exchan ers CHB-2418-B RHR Heat Exchanger Welds Pi es and Valve Weld Ma s 30A616-1 Weld End Detail -, Machined Backing Rings 30A616-4 Weld End Detail CHM-2067-C Feedwater Syst'm - Code Class 1 CHM-2068-C Recirculation System - Code Class 1 CHM-2069-C Mainsteam System - Code Class 1 CHM-2070-C Residual Heat Removal System Code Class 1 CHM<<2071-C Core Spray System - Code Class 1 CHM-2072-C CRD Hydraulig Return Line - Code Class 1 CHM-2073-C Reactor Wat'er Clean-up and RCIC-Code Class 1 CHM-7074-C High Pressure Coolant Injection Code Class 1 MSG-0018-C Residual Heat Removal System - Code Class 2 Pi in and Valve Han er Ma s CHM-2082-C Reactor Water Clean-up and RCXC Code Class 1 CHM-2083-C High Pressure Coolant Injection - Code Class 1 CHM-2084-C RHR System - Code Class 1 CHM-2085-C Feedwater System - Code Class 1 CHM-2086-C Recirculation System Code. Class 1 CHM-8087-C Mainsteam System Code Class 1 CHM-2089-C 'Core Spray System - Code Class 1
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BFNP Sr 4.6:G Page 169 FEEDWATER SYSTEM SEP 29 1981 BROWNS FERRY NUCLEAR PLANT DPP Assigned Weld No. Size Material GFW-2-1 24tl A106 GrB KFW-2-1 24 A106 GrB GFW-2-2 24" A106 GrB KFW-2-3 16"+ A106 GrB GFW-2-3 24 lt A106 GrB GFW-2-4 24 II A106 GrB KFW-2-4 ~ 24 l I A106 GrB KFW-2-5 24" A106 GrB GFW-2-5 241I A106 GrB KFW-2<<6 24lf A106 GrB KFW-2-7 24" A106 GrB KFW-2-8 24 II A106 GrB GFW-2-6 24 I I A106 GrB GFW-2-7 24 tl A106 GrB KFW-2-9 24" A106 GrB KFW-2-10 20lf A106 GrB KFW-2-11 20lf A106 GrB KFW-2-12 201 I A106 GrB GFW-2-8 1 2I I A106 GrB KFW-2-13 12" A106 GrB GFW-2-9 ] 21f A106 GrB GFW-2-10 12" A106 GrB
BFNP SI 4.6.G Page 170 SEP 29 l98'I DPP Assigned Weld No. Size Material KFW-2-14 1 2 II A106 Gx'B KFW-2-15 12It A106 GrB GFW-2-11 12ll A106 GrB GFW-2-12 12tt A106 GrB GFW-2-13 1 2l I A106 GrB KFW-2-16 1 2 II A106 GrB KFW-2-17 12" A106 GrB GFW<<2-14 A106 GrB GFW-2-15 1 2 II A106 GrB GFW-2-16 A106 GrB KFW-2-18 12tl A106 Gx'B KFW-2-19 1 2I I A106 GrB GFW-2-17 1 2 II A106 GrB GFW-2-18 24 II A106 GrB GFW-2-19 24 I I A106 GrB KFW-2-21 81l+ A106 GrB GFW-2-20 24lt A106 GrB
~
GFW-,.2-21 24ll A106 GrB KFW-2-22 24 II A106 GrB KFW-2-23 24k l A106 GrB GFW-2-22 241l A106 GrB
'FW-2-24 24" A106 GrB KFW-2-25 24" A106 GrB KFW-2-26 24ll A106 GrB
BFNP SI 4.6.G Page 171 SEP23 198l DPP Assigned Weld No. Size Material GFW-2-23 24 II A106 GrB GFW-2-24 24ll A106 GrB KFW-2-27 24 II A106 GrB KFW-2-28 2PII A106 GrB KFW-2-29 2PI I A106 GrB 2PI I A106 GrB KFW-2-30'FW-2-25 12" A106 GrB KFW-2-31 12" A106 GrB GFW-2-26 1 2I I A106 GrB GFW-2-27 1 2l I A106 GrB KFW-2-32 1 2 1l A106 GrB KFW-2-33 1 2 II A106 GrB GFW-2-28 12ll A106 GrB GFW-2-29 1 2ll A106 GrB GFW>>2-30 1 2 II A106 GrB KFW-2-34 1 2II A106 GrB KFW-2-35 12II A106 GrB GFW-2-31 '12" A106 GrB GFW-2-32 1 2I I A106 GrB GFW-2-33 1 2 II A106 GrB KFW-2-36 12lt A106 GrB KFW-2-37 1 2I I A106 GrB GFW-2-34 1 2l I A106 GrB KFW-2-38 A106 GrB KFW-2-39 1 2ll A106 GrB
HIS l80>>
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NZK 530 I+4 300 '70>> NZN NZC 240 NZF 2IO'R GR.2 Sr CR.2-1 OR W CR 2-4T CHE- 2.4 GA 2& CA 2 IT CA 294 CR 2 I KR 23S KA'2 3 KR ZVO KR 2<3~ KA 244 KA 2 KA 24 KA'2 KR2IT~ KR2i~
2-50 3 ~I Sr GR 2 53i Sl KR 250 KA-2 ~ /
GA 2 36 . GlhE-39 CA.ZHZ +49 +CA 2- 23 CA% 20 GA.Z l6 OR 240 M 6 ~CR 2 54 IZ GA'245 20 RESIDUAL I%AT CR 2 CR238 GA.21 233 GR 2% GR ~S +KR 246 22 249 R2 IS 'GA 2 lt GA29 KR2 36 &2 KA KR 2 1 KR/2 42 VALVE VALVE KA 2 KA 249 KA 2'll KRNI4 5 65A El. 580'9 4 3T KR 2-34 OR 2 5I 2 25 CRZIB IZING IZ +KR 2 l5 CR 2 31 24 RESeUAL HEAT OR 2 24'ES I DU+~AT I9 REMOVAL RETURN REMOVAL KA~S l5 IO KR~
14 t-CAN< '""1 9 OR-2 2T GA 28 s CR2
~KR2 4-24 VA)V 2 EL 5S6'8 PUMP 2 IA PUMP 2 IB KA-2 I A-2%3A KR 2 23 OR-2 30 KA 2 lr GR258 24 Cn >>U OI 01 VALVE I6 43A 4 IS '4 KR248 OR 2%
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waO eENTIFICATION Q SKXCATES PIECE NUMBER oo ~I>>
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BFNP
- SI 4.6.G Page 173 RECIRCULATION SYSTEM SEP 29 1981 BROWNS FERRY NUCLEAR PLANT DPP Assigned Weld No. Size Material GR-2-1 28" A358 w/seam GR-2-2 28" A358 w/seam KR-2-1 4 I I+ A376 304 7
GR-2-3 28" A358 w/seam GR-2-4 4tt A376 304 KR-2-2 28" A358 w/seam KR-2-3 28" A358 w/seam KR-2-4 4 II+ A376 304 GR-2-7 4tt A376 304 GR-2-8 28tt A358 w/seam KR-2-11 28" A358 w/seam KR-2-12 22" A358 w/seam KR-2-13 12tt+ A403 KR-2-14 1 2l t+ A403 KR-2-15 22" A358 w/seam GR-2-9 12 1 I A358 w/seam GR-2-10 12 A358 w/seam KR-2-16 1 21l A358 w/seam GR-2-11 ] 2lt A358 w/seam GR-2-12 A358 w/seam
'R-2-13 A358 w/seam KR-2-17 1 2ll A358 w/seam GR-2-14 1 2lt ~58, w/seam
BPNP SZ 4.6.G Page 174 SEP 29 l981 DEP Assigned Weld No. S1ze Material GR-2-15 1 2tl A358 w/seam GR-2-16 1 2 II A358 w/seam KR-2-18 12" A358 w/seam GR-2-17 1 2I I A358 w/seam GR-2-18 22 II A358 w/seam KR-2-19 1 2ll+ A403 GR-2-19 12ll A358 w/seam GR-2-20 12" A358 w/seam KR-2-20 12"+ A403 KR-2-21 12tt A358 w/seam GR-2-21 2ll A358 w/seam GR-2-22 1 21t A358 w/seam GR-2-23 12" A358 w/seam KR-2-22 A358 w/seam GR-2-24 12tl A358 w/seam GR-2-25 22I I A358 w/seam GR-2-26 22tl A358 w/seam GR-2-27 2811 A358 w/seam GR-2-26A 28't A358 w/seam KR-2-23 4tf+ A376 304 GR-2-28 28" A358 w/seam GR-2-30 4lt A376 304 KR-2-24 28" A358 w/seam
BFNP SI 4.6.G Page 175 SEP2S tSst DPP Assigned Weld No. Size Material KR-2-25 28 I I A358 w/seam KR-2-26 4 I I+ A376 304 GR-2-33 41l A376 304 GR-2-34 28l I A358 v/seam KR-2-33 28 I I A358 w/seam KR-2-34 22II A358 w/seam KR-2-35 12"+ A403 KR-2-36 1 2l I+ A403 KR-2-37 22" A358 w/seam GR-2-35 12ll A358 w/seam GR-2-36 1 2ll A358 w/seam KR-2-38 12" A358 v/seam GR-2-37 1 21 I A358 w/seam GR-2-38 1 2lt A358 w/seam GR-2-39 A358 w/seam KR-2-39 1 2 II A358 w/seam GR-2-40 1 2II A358 w/seam GR-2-41 1 2 II A358 w/seam GR-2-42 12tt A358 w/seam KR-2-40 1 2ll A358 w/seam GR-2-43 1 2l I A358 v/seam KR-2-41 1 2I I+ A403 GR-2-44 22II A358 w/seam
BFNP SI 4.6.G Page 176 SEP 29 198>
DPP Assigned Meld No. Size Material GR-2-45 12tt A358 w/seam GR-2-46 1 2 II A358 w/seam" KR-2-42 12"+ A403 KR-2-43 1 2II A358 w/seam GR-2-47 12lt A358 w/seam GR-2-48 12tl A358 w/seam GR-2-49 ] 2tl A358 w/seam KR-2-44 1 2 II A358 w/seam GR-2-50 12tl A358 w/seam GR-2-51 A358 w/seam GR-2-52 22lt A358 w/seam GR-2-53 28" A358 w/seam KR-2-45 28ll A358 w/seam GR>>2-54 28" A358 w/seam GR-2-55 28" A358 w/seam KR-2-46 28" A358 w/seam KR-2-47 28lt A358 w/seam GR-2-56 28" A358 w/seam GR-2-57 28" A358 w/seam KR-2-48 28" A358 w/seam KR-2-49 4tl+ A376 304 GR-2-58 28 I t A358 w/seam GR-2-59 28tt A358 w/seam
BFNP Sk 4.6.0 Page 177 SEP S>>SS1 DPP Assigned Weld No. Size Naterial KR-2-50 281 l A358 w/seam GR-2-60 A358 w/seam GR-2-61 281 I A358 w/seam KR-2-51 28 II A358 w/seam GR-2-62 28n A358 w/seam ~
GR-2-63 28 II A358 w/seam GR-2-63A 4n A376 304 GR-2-63B 4 I I+ A376 304 KR-2-52 A358 w/seam 4 I+
I A376 304 KR-2-53 GR-2-64 28" A358 304
REFQKNCE ORAWHOS 17KI767 ITW555 I KELLOCC 7296229 PIPE DATA CODE CLASS I ISTM A ISS KC 70 26 a 0.950 MOM. WLL CMS 2 IOIS 2 26
~WSS kMS<y1 KMS 2 IA KMS-2 IS KMS 2 95 KMS 2%
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$ KMS Kl l045%<2 KM'M5 KMS 2 87 KMS 26 KMS-2-ed KMS 2 65 KM5 2 5 KMSW61 KMS.2.5 KMS 2 65 XLa5IK'Z KM92 26~ KMSWIOS KMS WO CMS 2 S~ KMS 2 62 COMTAAED AT PONT 0 TNUEg AT PONT A Ol MSG~2I C QIEET I POCIRATIOM ~$
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BFNP SI 4.6.G Page 180 MAIN STEAM BROMNS FERRY NUCLEAR PLANT DPP Assigne'd Meld No. Size Material GMS-2-1 26I'6 A155 KC70 II GMS-2-2 A155 KC70 GMS-2-3 26" A155 KC70'155 KMS-2<<1 26" KC70 GMS-2-4 26" A155 KC70 GMS-2-5 26II A155 KC70 KMS-2-2 26I'l A155 KC70 KMS-2-3 I+ CS KMS-2-4 6II CS KMS-2-5 6II CS KMS-2-6 6II+ CS KMS-2-7 CS-
'MS-2-8 61 I CS KHS-2-9 61 I+ CS KMS-2-10 6 II CS KMS-2-11 6ll CS KMS-2-12 6lt+ CS KMS-2-13 6 II CS KHS-2-14 6II CS KMS-2-15 6l I+ CS KMS-2-16 6ll CS KMS-2-17, CS
BFNP SI 4.6.G Page 181 SEP 29 'I981 DPP Assigned Weld No. Size Material KMS-2<<18 6rr+ CS KMS-2-19 6ee CS KMS-2-20 CS KMS-2-21 6"+ CS KMS-2-22 6n CS KMS-2-23 CS KHS-2-24 26fl A155 KC70 KHS-2-25 26" A155 KC70 KMS-2-26 26" A155 KC70 GMS-2-6 26" A155 KC70 GMS-2-7 26" A155 KC70 KMS-2-27 26" A155 KC70 KMS-2-28 26" A155 KC70 GMS-2-8 26" A155 KC70 GMS-2-9 26 A155 KC70 GMS-2-10 26" A155 KC70 GMS-2-11 26" A155 KC70 KMS-2-29 26 II A155 KC70 KMS-2-30 26tl A155 KC70 GMS-2-12 2 6 II A155 KC70 I
GMS-2-13 26 1 A155 KC70 KMS-2-31 26lt A155 KC70 KHS-2-32 6si+ CS KHS-2-33 Il 6 .. CS.
BFNP, S f'Me.W.~
Page 182 SEP 29 1981 DPP Assigned Weld No. Material KHS-2<<34 6I I CS KMS-2-35 6ll+ CS KMS-2-36 CS KHS-2-37 6 CS KMS-2-38, 26" A155" KC70 GMS-2-14 26" A155 KC70 GMS-2-15 26lr A155 KC70 GMS-2-16 26ll A155 KC70 KHS-2<<40 6 I I+ CS KMS>>2-41 6II KMS-2-42 6II CS KHS-2-43 6II+ CS KHS-2-44 6II CS KMS-2-45 6 CS KMS-2-46 6II+ CS KHS-2-47 6" CS KHS-2-48 6" CS r
KHS-2-49 6ll+ CS KMS-2-50 6ll CS
'HS-2-51 61I CS KHS-2-52 26 I I A155 KC70 KHS-2-53 10 "+ CS KMS-2-54 26 II A155 KC70
f3FNP SI 4.6.G Pnme 183 SEF'29 1981 Dpp Assigned Meld No. Size Material KMS-2-55 26lt A155 KC70 GMS-2-17 26 I I A155 KC70 GMS-2-18 26 A155 KC70 GMS-2-19 26" A155 KC70 KHS-2-56 26lf A155 KC70 KMS-2-57 26 II A155 KC70 GMS-2-21 26 1 I A155 KC70 GMS-2-22 26" A155 KC70 KHS-2-58 26" A155 KC70 6 CS KMS-2-59 6 CS KHS-2-60 KMS-2-61 6"+ CS KHS-2"62 2 6ll A155 KC70 KMS-2-63 3l ly CS GMS-2-23 26>> A155 KC70 KHS-2-64 6 CS KHS-2-65 6" CS KHS-2-66 6" CS KMS-2-67 6ii+ CS KHS-2-68 6)i CS 6 CS KMS-2-69 KHS-2-70 CS KMS-2-71 6I I CS
BFNP SI 4.6.G Page 184 SEP 29 198l DPP Assigned Material Weld No. Size KHS-2-72 6" CS 61l+ CS KMS-2-73 6II CS KMS>>2-74 6 II CS KMS-2-75 2 6 II A155 KC70 KHS-2-76 26 II A155 KC70 GMS-2-24 26 I I A155 KC70 GMS-2-25 26ll A155 KC70 KMS-2-79 A155 KC70 KMS-2-80 26 I I A155 KC70 GMS-2-26 26lt A155 KC70 GMS-2-27 26" A155 KC70 GMS-2-28 26 II A155 KC70 GMS-2-29 26 I I A155 KC70 KHS-2-81 26 I I A155 KC70 GMS-2-30 26 I I A155 KC70 GMS-2-31 26ll A155 KC70 KMS-2-82 KMS-2-83 6"+- CS KHS-2-84 6" CS 61I CS KHS-2-85 61I+ CS KHS-2-86 6
BFNP SZ 4.6.G Page 185 SEP 23 198t DPP Assigned Weld No. Size Material KMS-2-89 6 I I+ CS KMS-2-90 6 II CS KMS-2-91 6II CS KMS-2-92 CS KMS-2-93 CS KMS-2-94 6II CS KMS-2-95 6ll+ CS KMS-2-96 6" CS KMS-2-97 6II CS EMS-2-98 6II+ CS KMS-2-99 CS KMS-2-100 CS KMS-2-101 61 I+ CS KMS-2-102 6II CS KMS-2-103 6 CS KMS-2<<104 2 6 II A155 KC70 KMS-2-105 26ll A155 KC70 KMS-2-106 2 6l I A155 KC70 GMS-2-32 26" A155 KC70 GMS-2-33 2 6ll A155 KC70 KMS-2-107 26 II A155 KC70 KMS-2-108 26ll A155'C70 GMS-2-34 2 6ll A155 KC70
'I REIEIIENCE CTIAHISIOS CWXSM AHO 4 S~~H-SQZ Cere CNPIC-SL St ANO SS AT lONTS S.
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'PigANAI SHOP WELD ~
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BFNP SZ 4.6.C Page 189 RHR SYSTEM SEP 2~ ~S8~
BROWNS FERRY NUCLEAR PLANT DPP Assigned Weld No. Size Material DRHR-2-3 2411 SS DRHR-2-4 2411 SS DSRHR-2-1 24" SS DSRHR-2-2 24" SS DRHR-2-5 2411 SS DRHR-2-6 2411 SS DSRHR-2-3 2411 SS DSRHR-2-4 2411 SS DSRHR-2-4A 2411 SS DRHR-2-7 2411 SS DRHR-2-8 2411 SS DRHR-2-9 2411 SS DRHR-2-12 24'll SS DRHR-2-13 2411 SS DSRHR-2-5 2411 SS DSRHR-2-5A 2411 SS r
DRHR-2-14 2411 SS DRHR-2-15 24 It SS DSRHR-2-6 2411 SS DSRHR-2-7 2411 SS DRHR-2-16 2411 SS DRHR-2-17 2411 SS DRHR-2-18 2411 SS
BFNP SZ 4.6.C Page 190 SEP 29 198~
DPP Assigned Weld No. 'Size Material DRHR-2-19 201l SS DSRHR-2-8 SS DSRHR-2-9 2ptl SS DRHR-2-21 20I I SS DRHR-2-22 2pll SS
-DSRHR-2-10 2 pit SS DSRHR-2-11 2pll SS DRHR-2-23 2plf SS TRHR-2-191 2pll CS to SS TRHR-2-192 2Ptt CS TRHR-2-193 20ft CS TRHR-2-194 2Ptt CS DHS-2-1 6" SS DSHS-2-1A 6" SS DSHS-2-1 6 SS DSHS-2-2 SS DSHS-2-3 SS DSHS-2-4 6" SS DSHS-2-5 6 SS DHS-2-2 6" SS DSHS-2-6 SS DSHS-2-7 6,r SS DSHS-2-8 6t SS
BFNP SI 4.6.G Page 191 SEP 29 1981 DPP Assigned Weld No. Size Material DHS-2-3 6", SS DSHS-2-9 611 SS DSHS-2-10 6" SS DSHS-2-11 6 SS DSHS-2-12 6 SS DSHS-2-13 611 SS DSHS-2-14 611 SS DSHS-2-15 6" SS DSHS-2-16 611 SS DHS-2-4 611 SS DHS-2-5 611 SS DSHS-2-19 6" SS 6 SS DHS-2-6 DHS-2-7 CS to SS 611 CS TRHR-2-479H 611 CS TRHR-2-479G 6 CS TRHR-2-479D TRHR-2-479B 6" CS
TCS. Z- 401 TCS- 2. 403 TCS 2 402 TSCS-Z 404 TC6 405 TCS-2-406~
VALVE NSB 240s f
NSA 120~
VALVE TCS.2 -4IT TSCS 418 TCS - 2 419
~~stet.s.sso TCS- 2-421 TCS 422 TCS 2-407 14 B 14 A TCS 423 TSCS-2-408 TSCS.2 -424 TSCS . Z'- 4C9 2.425 TSCS ~
T CS - 2 410~
is ~ TCS-2-426 OCS-,2-14'SCS
~DCS-2-5 I ~ 2-9~ VALVE DSCS- 2- 2 VALVE:, OCS- 2-Tq 13 8 608Al.VE t3A
/ VsILVE 12 8 ~ EL 605'le REF OWGS TVA 4TXITTZ EL IZ A TVA 4TVI335 IS X168 DRAVO E2456IC.34 X16A bRAVO E245610.35 DCS-2-sI
- DCS 13 DCS-2-12 DCS-2.3 REvlSION NOTES:
REROUTE CORE SPRAY LINE MW D ~ CPAVO FIELD WELD WELD NO.
0 DS ~ DPAVO SII OP YIELD C ttssssttttt YALLCY AUtssOsslt Cl wl%%e ss sssts tsssssttscs V/KLO IDFNTIFICATION CD CORE SPRAY SVSTEII BROWIIS FERRY NUCLEAR PLANT
~ ~
CfIM 2071 C Rl
HFNP SI 4.6eG Page 193 SEP ~9 1981 CORE SPRAY SYSTEM BROWNS FERRY NUCLEAR PLANT UNIT 2 DPP Assigned Weld No. ~Inches Material TCS-2-401 10 CS to SS nozzle to safe end 2-402
'ize TCS-. 10 CS TCS-2-403 10 CS to SS TSCS-2-404 10 CS TCS-2-405 12 CS to SS TCS-2-406 12 CS to SS TCS-2-407 12 CS TSCS-2-408 12 CS TSCS-2-409 12 CS TCS-2-410 12 CS to SS TCS-2-417 10 CS to SS nozzle to safe end TSCS-2-418 10 CS to SS TCS-2-419 10 CS TSCS-2-420 10 CS TCS-2-421 CS to SS TCS-2-422 12 CS to SS TCS-2-423 12 CS TSCS-2-424 12 CS TSCS-2-425 12 CS TCS-2-426 CS to SS
BFNP SI 4.6.G Page 194 SEP 29 1981 CORE SPRAY SYSTEM BROWNS FERRY NUCLEAR PLANT UNIT 2 DPP Assigned Size Weld No. ~aches) Mat:erial DCS-2-14 12 SS DSCS-2-9 12 SS DCS-2-7 12 SS DCS-2-13 12 SS DCS-2-12 12 SS DCS-2-5 12 SS DSCS-2-2 12 SS DSCS-2-1 12 SS DCS-2-4 12 SS DCS-2-3 12 SS Reference Drawings:
TVA 47K1772 TVA 47W335-15 DRAVO E24561C-34 DRAVO E24561C-35
RCRD 2 49 85-TT RCRO 2-48 RCRD-2-43 RCRDS 2-I N9 RCRO-2-45 l46r I
I 8'T04 RCRO 2-4T REDUCER I FLOW I I RCRDSw2-3 6 TO4'EDUCER RCRO-2-46 I I
RCROS-2-2 RCRD-2-44 8 X8'X8 TEE RCRD-2-40 CONT, FROM CMM-2073-C REF. OWG. REV I SICH HOTES:
TVA 47KI648-5 VNIT HO. WELD NO. t REROUTE CRD RETURN UHE REACTOR COHTROL ROD DRIVE NYDRAVLIC RETURN LINE M~
YCFFFFCCCCC YALLCY AUYHOWFYY LJa J
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~ t&NW
~ 2072-C
BFNP SI 4.6.G Page 196 SEP 29 ~S8~
CRD HYDRAULIC RETURN BROWNS FERRY NUCLEAR PLANT DPP Assigned Meld No. Size Material RCRDS-2-1 Sll CS RCRDS-2-2 6 CS II RCRDS-2-3 S CS RCRD-2>>40 4tl CS RCRD-2-43 4l I CS RCRD-2-44 4 II CS RCRD-2-45 4ll CS RCRD-2-46 4ll CS RCRD-2-47 4 II RCRD-2-48 4ll CS RCRD-2-49 4ll CS to SS
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UNIT NO WELD NO C fmT TTaTT DS MAYO SHOP WELD TCFEATCTCC VAF.T.CT AMTREETAETT REAI '.OR'ATFR I ~ EIRRA AF RRRT ~ FNREECTEROs CLEAH UP REACTOR CORE WFLD IDFIITITICATIOH ISOLATION CODLING RFACTOR WA ER CLEAN UP ANO RCIC
~
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BFNP SI 4.6.G Page 198 REACTOR WATER CLEANUP AND REACTOR CORE ISOLATION COOLING SFP g 9 198 I BROWNS FERRY NUCLEAR PLANT DPP Assigned Weld No. Size Material DRWC-2-lA 6II SS DRWC-2-1 6)I SS DSRWC-2-1 SS DRWC-2-2 SS DRWC-2-3 6" DSRWC-2-1A 6IP SS DSRWC-2-2 6" SS DSRWC-'-3 SS DSRWC-2-4 61I SS DSRWC-2-5 6 II ,SS DSRWC-2-6 6II SS DSRWC-2-7 6 II SS DRMC-2-4 6IP SS DRMC-2-5A 6" SS DRMC-2-5B 61I SS DSRWC-2-8 4II CS DSRWC-2-9 4 II CS DRWC-2-58 4 II CS DRWC 60 4 II CS DRWC-2-59 4 II CS
8FNP SI 4.6.G Page l99 SEP 29 t981 DPP Assigned Weld No. Size Material TRCIC-2-2 6II CS TRCIC-2-3 6 II CS TRCIC-2-4 6 II CS TRCIC-2-7 6 II CS II TRCIC-2-1 S CS TRCIC-2-1A g II CS
UNIT 2 26 MAIN STE>M MLE~K2 THPCI 2-55 69 THPCI-2 66A THPCI 2-67 THPCI- 2-68 3S THPCI 6BA THPCI-2 59 UNIT 2 TH PC I 70 24 FEEDWATER ~E. 51 5 THPCI 2-70A THPCI-2-7( THPCI 2-65 IS TMPCI-2 72 THPCI-2 63 67 I3 THPCI-2-73 THPCI-2 62 THPCI 2 6I X 5 THPCI-2-74 THPCI 2 75 THPCI 2-75 THPCI 2-75A REF. DWGS:
TVA 47W335 I2 I6 TVA 47W335 II THPC I-2-82 TVA 47'567 r5 Ih III 0 INDICATES PIECE NUMBER 5I 00 c
R THPC I N-N M Ch Q ~
TVA W LD NO. O C3 UNIT NO HIGH PRESSURE TCHIItssct YALLCT AUTHORITY COOLANT INJECTION Nba V fleer N4NCTcs WELD IDENTIFICATION HIGH PAESSVAE COOLAN'T INJECTION BROWNS FERRY NVCLEAR PLANT CHIP2074C
BFNP SI 4.6.G Page 201 HIGH PRESSURE COOLANT INJECTION SYSTEM SEP 28 ]98~
BROWNS FERRY NUCLEAR PLANT DPP Assigned Weld No. Size Material THPCI-2-61 14" CS THPCI-2-62 14" CS THPCI-2-63 14" CS THPCI-2-65 16" CS THPCI<<2-66 10 CS THPCI-2-66A ] pll CS THPCI-2-67 10" CS THPCI-2-68 CS 101'0" THPCI-2-68A CS THPCI-2-69 1PII CS THP CI-2-70 10" CS THP CI-2-70A 1P I I CS THPCI-2-71 10" CS THPCI-2-72 1PII CS THPCI-2-73 1PI I CS THPCI-2-74 1PII CS THPCI-2-75 10 CS THPCI-2-76 101' CS THPCI-2-76A pit CS THPCI-,2-82 1P I I CS
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BFNP SI 4.6.0 Page 222 SEP 29 l98I I.ist of Drawin s - Unit 3 Reactor Vessel Drawin ~ No. Title CHM-1077-h Reactor Vessel Seam Welds CHM-1090-h Control Rod Drive Penetration {Detail)
CHM-1091-A Suppnrt Skirt Weld CHM-1094-A Nozzle to Vessel Weld CHM-1095-A Vessel and Head Welds CHM-2001-C Vessel Stud Locations CHM-2002-C Control Rod Drive Penet'ration {Locations)
CHM-2046-C Development of Biological Shield and Reactor Vessel Seam Welds CHM-2102-A Closure Head Assembly MSG-0020-A Reactor Vessel Clad Patches Residual. Heat Removal Heat Exclian ers CHM-2418-B RHR Hent Fxchanger Welds
'I iin ~
and Valve Weld Ma is 30A616-1 Weld Fnd Detail Machined Backing Rings 30A616-4 Meld End Detail CHM-2138-C Feedwater System - Code Class 1 CHM-2139-C Recirculation System - Code Class 1 CHM-2140-C Mainsteam System Code Class 1 CHM-2141-C Residual Heat Removal System Code Ciass 1 CHM-2142-C Core Spray System Code Class 1 CIIM-2143-C CRD Hydraulic Return. Line Code Class 1 CHI 1-2 I 44-C Reactor Water Clean up and RCIC-Code Class I CIIM-2 I 4 5-C H I gli Pressure Coolant Inj cc t ion-Cnde Class 1 CHM-2405-C Ma insteam Code Class -2 CHM-2406-C RHR Slnit<lown Siipply - Code Class 2
BFNP SI 4.6.G Page 223 SEF 29 >os List of Drawin s unit 3 (continued)
Pi in And Valve Han er Ma s Drawin No. Title ~Pa e No.
CHM-2146 Reactor Water Clean-up and RCIC Code Class 1 CHM-2147-C High Pressure Coolant Injection Code Class 1 CHM-2148-C Feedwater System Code Class 1 CHM-2149-C Recirculation System - Code Class 1 CHM-2150-C Mainsteam System - Code Class 1 CHM-2152-C Core Spray System - Code Class 1 CHM-2153-C RHR System Code Class 1 CHM-2410-C RHR Shutdown Supply Code Class 2 CHM-2411-C Mainsteam - Code Class 2 CHM-2412-C RCIC - Code Class 2 CHM-2413-C HPCI Pump Discharge Code Class 2 CHM-2416-C RHRSW Code Class 3 CHM-2417-C EEL - Code Class 3 CHM-2425-C Closed Cooling Water Code Class 3 CHM-24 29-C Fuel Pool Cooling System Code Class 3
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REC I RCULAT lON I NLE T UNITS I,Z,A-MAIN STEAM ESCHEL UNITS. I, 2,3 RECIRCULATION OUTLET UNI TS 2,3 FE EDWATER UN I TS l,2,3 CQR E SPRAY UN TS l,2,3
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TYPICAL OF:
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WA VESSEL OO NOZZLE NOZZLE TO VESSEL WELDS BRO'NNS FERRY NUCLEAR PLANT
TYP ICAL OF-gET PUMP INSTRUMENTATION U N ITS 2,3 CA VESSEL 0 CO M
0 M'5 I cM NOZZLE oc)
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Pl l9 ROw 2I OOOO 00000000000 acI I 5 ROYY 23 000 0000000000 0 I I ROW 25 00 00000000Q ASSUMED NORTH LOOK~
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UNITS I-5 CLOSURE HEAD ASSEMBLY WELD LOCATIONS QJQAITTlD AWtOVlD CH-M-2IO "A
BFNP SI 4.6.Q FLANGE SEAL SURFACE Page 243 9 t98>
NO. I d
NO, 2 NO. 3 NO. 4
'9 NO. 5 NO' N4A N4D FEE DWATER FEE DWATER NOZZLE NOZZLE I
2lOD TENNESSEE VALLEYALITHOR)TY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT UNlTS I" 3
'REACTOR YESSEL CLAD PATCHES SClLtt CNAWN tttIMlttlD Aft'tD OAtt ttttn oi tttttn TRAC10 MSG -A CNltlttD
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m MN MW RHRG-l2- (NOZZLE SlDE) f 5-ZV.8l RDO /VNF A-A'ECTION'D-B'e'r REV530MS RHRG-l4- . ~ t <)s.t r TED'. - e vw eG e 8ROuNS FERRY NUCLEAR PLANT SEMION Nf5 l3 RHR HEAT EXCHANGER WELOS I
-"'<~/~ 'cion-zoon e
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A= nominal outside diam~ter kYhen actual lDis less than nonIina/ leave parents me&/
8= nominal inside diameter be~nd'achined surfeces C=machi nod inside diemen er unoisfurbed.
t=nofni'nial eall thickness Not 7"o sea/e WELDING SPECIFICATION TYPIC' O'I= PIPINC MECHANICAL".
BRGWNS FERRY NUCLEAR V/ELD END DETAIL 4fl AV(lvwlrrf PI ANT MACHINED BACKING RINGS GENf RAL TKNNLlS5M MALL'cY ArITNOlt1TY
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>Mewviat 't o > g a t.~ t e '~ OA6sw
N4C N48 N4A N4F N4 E. N4D ISO 90 3Po p4 33T 270~ 2I0 CFVI-3 I 4 CFw-3-i 7 KFIV3 IS Gf sV 3-I I GF W-351 KFW.3 I 9 I GFW-398 GFW 3-34 l2 Kf'w-3.I 8 KF W3-!6 KF'W 344 IO KfSV367 KFW 336 KFW- 47 8 CFW.3.!3 KflV3-33 GFw-3-i 6 CF \V-340 GF W.3.33 Kfw3-35 KFW-3-39 KFw 334 KF W-332
'KFW-3<O KFW-3-4I KFW+l2 KFW 3-43 17 fw 3 27 CFW 3.3O KFW3 8 l3 ie KFW-3-44 , KFW-3-45 l4 GFW3-26 KFW-3-7 GFA3-!S GFW3-!2 GF W ~ Kf w-3-38 kfw-3-!2 Gf'w-3-29 VALVE K~ iV3 IO KfI%388 29A G W3-9 ALVE 86 6 2 KFW3-26 I
GF'W-3-2 4 CFW 3.3 K r W-3-4
'fW-3-3I 20 Cfw3-2S KfK3.27 kfWQ-2 S KF W-3-24 VALVE 96 A
!iiiii rs GFW3.4 Ira+ VALVE CFW-3-6 GF W3-7 EL 574 S Cfw-3-8 KFW-3-!I KFW3-3Q KFW329 CFW3-24 GFW3.23 VALVE 28B ar -~
(Q4 Gf W3-2I CFW3-I9 I!!Iil
~VALVE.
't06B 6,I I REVISION NOTES:
8 RCIC GFW 3 22 KF W-3 2I KFW3.6 Kfw3-23 KF5-3-22 i6 FIPCI
'KflV3-I GF W-3-S bD REF. DWGS.
TVA 17KI545 I ' IO W TVA 47iV335-2 CFW-3.! KF W-3-S 6 E '729 E I 52 U3 K FVV3-4 0 INDICATES PIECE NVM8ER I Xfw.N N SS>eHSSSSS YALSCT AVIHOSIJY
~ mls W 10elS tOOOUCiQe K ~ KELLOGG SHOP WELD WCL 0 NO. WELD IDENTIFICATION RE AC T OR fECOWA TER STS T C M G<GE FIELD WELD tJNI T NO.
BROWN'5 f CRRT NUCLEAR PLANT Rent'38
BFNP SI 4.6.G page 248
.SEP 29 198'f DPP Assigned Sizes Weld Nc. Inches GFW-3-1 24 A106 Gr B KFW-3-1 24 KFW-3-3 16 GFW-3-2 24 GFW-3-3 24 GFW-3-4 24 KFW-3A 24 KFW-3-5 24 GFW-3-5 24 KFW-3-6 24 KFW-3-7 24 KFW-3-8 24 GFW-3-6 24 GFW-3-7 24 KFW-3-9 24 KFW-3-10 20 KFW-3-11 20 KFW-3-12 20 GFW-3-8 12 KFW-3-13 12 GFW-3-9 12 GFW-3-10 12 KFW-3-14 12 KFW-3-15 12 GFW>>3-11 12 GFW-3-12 12 GFW-3-13 12 KFW-3-16 12 KFW-3-17 12 GFW-3-14 12 GFW-3-15 12 GFW-3-16 12-KFW-3-18 r 12 KFW-3-19 12 GFW<<3-17 12 GFW-3-18 24 KFW-3-21 8 GFW-3-19 24 GFW-3-20 24 GFW-3-21 24 KFW-3-22 24 KFW-3-23 24' GFW-3-22 24 KFW-3-2'4 24 KFW-3-25 24 KFW-3-26 24 GFW-3-23 I 24
~ KFW-3-24 24 KFW-3-27 24
BFNP SI 4.6.G page 249 SEP 23 )98l DPP Assigned Sizes Meld No. Xachee Narerial KFM-3-28 20 A106 Gr B KFM-3-29 20 KFW-3-30 20 GFM-3-25 12 KFW-3-31 12 GFM-3-26 12 GFM-3-27 12 KFW-3-32 12 KFW-3-33 12 GFW-3-28 12 GFM-3-29 12 GFW-3-30 12 KFM-3-34 12 KFW-3-35 12 GFW-3-31 12 GFM-3-32 12 GFW-3-33 12 KFW-3-36 12 KFW-3-37 12 GFW-3-34 12 KFW-3-38 12 KFM-3-39 12 KFM-3%0 12 KFW-3-41 12 KFW-3-42 12 KFM-3&3 12 KFW-3%4 12 KFW-3>>45 '12
N2E, N20 N2C N2B NZA NIA N2K N2J N2H N2C N2F ISO I 50 t20 90 60 30 0 330 300 270, 240O 2IO GR.3-59 CRB.37m GR3-40 CR3.43 GR 3.47 CR-3.50 324 GR3.2 I CR3.t7 'GR3 l4 CR3.ll KR.3-50 37 . 5 I 1 5 NI.3 38 KR339 R-3 40 hR-3W IS -3%I Rt3 18 KP-3.I7 R 3.42 KR3.44 3'>23 GR-3 3.36 GR3-39 R3 l6 3 I3 GR.3+i 0 GR-3 49 ~r KR3 t6 KR.3-4 5
'R-3.54 3.IO 2
GR-3.6 I GR.3.5 5 20 RHR GR3-35 GR322
-3l
.KR-396 3.4 I CR34 /R3 2I CR3~2 CR3 llR 3-I I KR-335 KR333 Ko-34 I KR-3 4 VALVE VALVEKR3 KR.3.I5 65B '5A EL. 580 9" KR-3-3 4 CR-3-44 GR3.52 GR.3 2 5 KR.3 t2 GR'3 5I GR.3.8 I9
! G R-3-26 CR 3-18 %-3.l 5 KR.3 25+ 24 RHP. RETURN R-3 3 KR.3 4 24 RHR RETURN KR-3-26 GP-I-7 KR3-2 4 GR-3-33 IO
~
KR-3. 2 GR-3 29 GR-3 3 GR.3.2 8 CR.3- 2 l4 9 CR-3.27 VAI.VE Gft3.1 VALVE
~ 53B EL. 556' 53A PUMP 3-IB PUMP 3. I A GR.3-6 4 KP 323 IL$I3 I V LVE~+359 VALVE KR 3 47 43A 43B M
/ 0 ec-w r/ ~g GR-3 62 CR 56 IJl ~
GR-3-63 REWBIOtt . mTES:
GR-3.638/ CO GR-3.6 3A CR-3 57 4 4" OECONTAMINATION QQJ3NTAMINATIQN CR-3-C CR-3. 30 KP.-3 53 KR-3-48>
REF. OhtCS. TC@tef$ $ CC VALLCY AUT~T
.-'R-3.52 'I TVA 47K I54 4 -t Aa, ~ Ol Cole t%4C10r UN IT NO. MtELO IDENT'IFIC AT ION K: KELLOGG SHOP wEI.O GE I53F 754 REC IRCULAT ION 5V5 TELI G:CE FIELO WELP RECIRCULATION KELLO GG BF 2 I80 BROW%5 FER RV NUCLEAR PLANT wELO NO.
O INOICATES PIECE NUVBER p+ ~
1 ~ mv.. -- CHM2I39~C -
)
BFNP SX 4.6.G page 251 SEI'29 j981 DPP Assigned Sizes Weld Ne. Inches Material GR-3-1 28 A358 w/seam GR-3-2 28 A358 w/seam KR-3-1 4 A376 304 GR-3-3 28 A358 w/seam KR-3 2 28 A358 w/seam KR-3-3 28 A358 w/seam KR-3-4 4 A376 304 GR-3A 4 A376 304 GR-3-7 A376 304 GR-3-8 28 A358 w/seam KR<<3-ll 28 A358 w/seam KR-3-12 22 A358 w/seam KR-3-13 12 A403 KR-3-14 12 A403 KR-3-15 22 A358 w/seam GR-3-9 12 GR-3-10 12 KR-3-16 12 GR-3-11 12 GR-3-12 12'2 GR-3-13 KR-3-17 12 GR-3-14 12 GR-3>>15 12 GR-3-16 12 KR-3-18 12 GR-3-17 12 GR-3-18 22 KR-3-19 12 A403 KR-3-20 12 A403 GR-3-19 12 A358 w/seam GR-3>>20 12 KR-3-21 12 GR-3-21 12 GR-3-22 12-GR<<3-23 12 KR-3-22 12 GR-3-24 12 GR-3-25 22 GR-3-26 22 GR-3-27 28 GR-3-28 28 KR-3-23 4 A376 304 GR-3<<29 28 A358 w/seam KR-3-24 28 A358 w/seam KR-3-25 28 A358 w/seam KR-3-26 A376 304 GR-3-30 A376 304 GR-3-33 A376 304 GR-3-34 28 A358 w/seam
.KR-3-33 28 A358 w/seam KR-3-34 22 A358 w/seam
BFNP SI 4.6.G Page 252 SEP 29 1981 DPP Assigned Sizes Weld No. 1nahes Material KR-3-35 12 A403 KR-3-36 12 A403 KR-3-37 22 A358 w/seam GR-3-35 12 GR-3<<36 12 KR-3-38 12 GR-3-37 12 GR-3-38 12 GR-3-39 12 KR-3-39 12 GR-3%0 12 GR-3-41 12 GR-3-42 12 KR-3-40 12 GR-3-43 12 GR-3-44 22 KR-3-41 12 A403 KR-3-42 12 A403 GR-3-45 12 A358 w/seam GR-3-46 12 KR-3-43 12 GR-3-47 12 GR-3-48 12 GR-3%9 12 KR-3%4 12 GR-3-50 12 GR-3<<51 22 GR-3-52 22 CR-3-53 28 KR-3-45 28 GR-3-54 28 GR-3-55 28 KR-3-46 28 KR-3-47 28 GR-3-56 28 GR-3-57 28 GR-3-58 28 KR-3-48 28 KR-3-49 4 GR-3-59 28 KR-3-50 28 GR-3-60 28 GR-3-61 28 KR-3-51 28 GR-3-62 28 GR-3-63 28 GR-3-63A 4 A358 GR-3-63B 4 A358 KR-3-52 28 A358 w/seam KR-3-53 4 A358 w/seam
'GR-3-64 28 A358 w/seam KR-3-54 KR-3-55
KhtS 3.22 KtAS.3-2l KtA 5-3. 20 N3A N3D 288.
KM53 19 i
KM53 l03 KM5.3 I 8 KMS3 IOZ KMS-347 KM5-3-IOI KtA5-3. I 6 Khl5-3 IOO KLIS.3.l 5 GMS-3 8 GM5-3-34 yKMS-3. 99 KM5.3. I 4 y KXI5-3-28 KM5.3- l08 KIA5.3.98 KMS 3-97 KMS.3 l3 5 KM 5-3. IO7 KM5.3.27 KMS 3 96 KM5-3.:2; KMS-3. 95 GM5-3 33 KMS-3 94 KM53 II Kh15-3 93 GMS-3. 7 KIA5-3 92 KM5-3 IO KMS 3 9I KMS-3 90 KM53 9 KM5-3.89 KM 5-3.8i Qi<aa KMS 3 88 KMS 3 87 KMS-3-7 3.6 KM5.3. 86 KIAS KM5383 KIAS -3. 8 5 KMS-3. 5 KMS-3.8 4 KMS 3. 4 y i@AS-3.83 KMS-3-3 I
I LINE A CA ELM6 7 ~LNE D GM5.3-6 GMS 3.32 KMS-3-2 5 00 KM5 2 4 KM 5.3-IO5 o C l7 KM5.3 2 KM53-26 K'4l 5-3'IO4 KM5382 KM5-3 106 8
II6 CC)
A GhIS-3-5 CD CM5 3-3 I lt GMS-3. 4 CM5-3.30 KMS 3- I GMS-3-3 REF'. DWC5. CMS3 27 I CMS-3'I TVA 47 Kl 767 Kv 5-3-8 I REVISION IIOTES:
I GMS-3.2 TVA 47W33 5 -I. CM5.389 KELLOCC 729E. 229 I
CM5 M8 I
Q INDICATE5 PIECE NUMBER Tt'5555t aeALLtT *VaaaOAITT
~agsoe ae eoea ~ raaaagegea UNIT NO, WELD IDENTIFICATION wELD NO. REACTOR MAIN STEAhl SYSTEIA
, GTCE FIELD wELD BROWN5 FERRY NUCLEAR PLANT CH M2I40
N3B N3G KM53- 66 252 KIA53 65 GM5.3 I7 KM5-3-6 4 GMS-3.26 KM5-3-55 KM5.3. 69 KM5-3-80 KMS-3-68 KMS-3-67 KM5 72 IO KMS-3-7 I l5 KMS-3.54 KM5-3-70 'M53-79 CMS.>l 5 KM5-3.7 5 KIA5.3-74 iE KM53.37 GM5-3-I 6 CMS-3. 25 K MS-3-73 K@53-36 KM 5-3-35 l4 KM5 N2 CMS-3 24 KM5.3-3 4 KMS-Nt KM5 3 33 KMS-3 40 KM5-3. 59 KM 5-3.32 l3 KM5-3-60 Kv5344i <<5347 KMS 3 6I
<MS"-4 ~-34I KM53 50 KM5 349 KM5-3.56 EL 586' LINC B LINE C KM5.3 3I CMS 3I4 KM53 53 KM5.3.76 K MS.3.38 l2 GMS-3 l3 KM5.3.52 GMS3.2 3 OM5 322 IO HPIG GM53.2 I M W GMS-3 l2 EL 568 I I II KMS 3-30 KM53.63 KM535T f KM5 3.29 3 RGIC KMS-356 N CMS II
+ ~
GRIS 3'20 GM5-3-IS M5.3 IO REF. DWGS.
GMS-3 I9 CG GMS-3 9 TVA 47K1767 TVA 47 W33 5 -I IIEVISION . IITESI KELLOCG 729E229 Q INDICA'TE5 PIECE NUMBER SS!!!!CSSCC VALLCV AUTMOIIISV S!!!SS!! Or ~e teeeVCS~
KSKCLLOCG 5NOP wELD MAIN STEAM wELD NO. WELD IDEN T I ICATION REACTOR MAIN STCAM SYSTEM f
GACE FIELD wCLO BROWIIS FERRY NUCLEAR PLANT
BOP SZ 4.6'.G Page 255
'SEP 29 1981 DPP Assigned S ises Weld No. Inches Meterfel GMS-3-1 26 A155 KC70 GMS-3-2 26 GMS-3-3 26 KMS-3-1 26 GMS-3A 26 GHS-3-5 26 KMS-3-2 26 KMS-3-3 6 CS KMS-3A 6 CS KMS-3-5 6 CS KHS-3-6 6 'CS KMS-3-7 6 CS KMS-3-8 6 CS KMS-3-9 6 CS KMS-'3-10 6 CS KMS-3-11 6 CS KMS-3-12 6 CS KMS-3-13 6 CS KMS-3-14 6 CS KMS-3-15 6 CS KMS-3-16 6' CS KMS-3-17 CS KHS-3-18 6 CS KMS-3-19 6 CS KMS-3-20 6 CS KMS-3-21 6 CS KMS-3-22 6 CS KMS<<3-23 6 CS KHS-3-24 26 A155 KC70 KHS-3-.25 26 KMS-3-26 26 GMS-3-6 26 GMS-3-7 26 KMS-3-27 26 KMS-3-28 26-GMS-3-8 26'6 GMS-3-9 GMS-3-10 26 GHS-3-11 26 KHS-3-29 26 KMS-3-30 26 GMS-3-12 26 GMS-3-13 26 KHS-3-31 26 KMS-3-32 6 CS KMS-3-33 6 CS KHS-3-34 6 CS KMS-3-35 6 CS KMS-3-36 ,6 CS KMS-3-37 6 CS KMS-3-38 26 A155 KC70 GMS-3-14 26 A155 KC70
BFNP SI 4.6.G Page 256 SEP 29 f981 DPP Assigned Sizes Weld No. Inches Mscscisl KMS-3-40 6 Cs KMS-3%1 6 Cs KMS-3-42 6 Cs KHS-3-43 6 Cs KHS-3-44 6 Cs KMS-3%5 6 Cs KMS-3-46 6 Cs KMS-3-47 6 Cs KMS-3-48 6 Cs KMS-3-49 6 Cs KHS-3-50 6 Cs KMS-3-51 6 Cs KMS-3-52 26 A155 KC70 KHS-3-53 10 Cs GMS-3-15 26 A155 KC70 GMS-3-16 26 KHS-3-54 26 KMS-3<<55 26 GMS-3-17 26.
GMS<<3-18 26 GMS-3-19 26 GMS-3-20 26 KHS-3-56 26 KMS-3-57 26 GMS-3-21 26 GMS-3-22 . 26 ~
KHS-3-58 26 KHS-3-59 6 Cs KMS-3-60 6 Cs KHS-3-61 6 Cs KHS-3-62 26 A155 KC70 KMS-3-63 3 Cs GMS-3-23 26 A155 KC70 KHS-3-64 6 Cs KMS-3-65 6- Cs KHS-3-66 r 6 Cs KMS.-3-67 6 Cs KMS-3-68 6 Cs KHS-3-69 6 Cs KMS-3-70 6 Cs KMS-3-71 6 Cs KMS-3-72 6 Cs KMS-3-73 6 Cs KMS-3-74 6 Cs Cs KMS-3-75 KHS-3-76 '6 6 A155 KC70 GHS-3-24 26 GMS-3-25 26 KMS-3-79 26 L
KHS-3-80 26
.GMS-3-26 26 GMS-3-27 26
BFNP SI 4.6.G Page 257 S~~ 89 198'J DPP Assigned Sizes Weld No. Inches Material GMS-3-28 26 A155 KC70 GMS-3-29 26 KMS-3-81 26 GMS-3-30 26 GMS-3-31 26 KMS-3-82 26 KMS-3&3 6 CS KMS-3-84 6 CS KMS-3-85 6 CS KHS-3-86 6 CS KHS-3-87 6 CS KMS-3-88 6 CS KMS-3-89 6 CS KMS-3-90 6 CS KHS-3-91 6 CS KMS-3-92 6 CS KMS-3'-93 6 CS KHS-3-94 6 CS KMS-3-95 6 CS KHS-3-96 6 CS KMS-3-97 6 CS KMS-3-98 6 CS KHS-3-99 6 CS KHS-3-100 6 CS KMS-3-101 6 CS KMS-3-102 6 CS KHS-3-103 6 CS KMS-3-104 26 A155 IC70 KMS-3-105 26 A155 IC70 KMS-3-106 26 A155 IC70 GMS-3-32 26 A155 IC70 GMS-3-33 26 A155 IC70 KMS-3-107 26 A155 IC70 KMS-3-108 26 A155 IC70 GMS-3-34 26 A155 IC70
0 REFERENCE DRAVIN6 5 ATRI568 IICIITAm~ 4TW335 4 AHO 6 4TW452 SQIIES
~391a AT POAIT DRAVO E2456IC 5I. 52 AIO 55 Loca-3~
~ ESRIR 54 yFerI m OeIR-5 ~
O s'rrrrcrrrr ~rrrr9 P f/'4
~5 ~ 4.OSRI44 54 I
g T449 D'OR%-5-15 OUI-5 l4 DSRHR TRHR 5 I92 3W L43I644 SCl JA2 0 Ch Ot
~ e ~m Co 63 TER 5494 CD QO
'l 0Ar ~ ICVI4rONS BRQWNS FERRY NUCLEAR PLANT IAAT e5 RESIDUAL IEAT REIIOIAL SISTOI
&ORWO FlELO WELD RTSIDVALICAL REI40rIAL WELD MO WELD IDGCKWS, OS~DRAVO SIIOP WELD I4EAD SPRAT VENT HO.
T ~ TYA
-II 2III@
OSAGE-S'4
~ 2 I OSRIIR S S BROWNS PER RT W CLEAR PlANT LAIT4S RKSeIIIL IITAT SKkOVAL SISTISI
%CLO IOCATICNS
p-DSHS~
14 6%i p DSHS.S< l pOSHS A DHS 3'5-OSHS-PO>>
TRHR MS50 DSHS 3'l0
~TRHR'3 4550 DSHS-5%
OHS 3 l OSHS 3'HS'3S!
OSHS 5-8 OHS 55 i
TRHR 545SA>>
OHS 3%
~OHS-3-r TRHR 3'450K Crt
~ Wcn M
Ca OSHS ~w ~N
~OSHS SHS 5+
mew Q 4 t4 OA
~
QD CO BROS+ ~RT gggg AR ~HT RESOUAL ~ R~
LMt s5 WIO LOC~
STSTO4
BFNP SI 4.6.G Page 261
~~F'89 198l DPP Assigned Sizes Weld No. Inches Material DSRHR-3-8 6 SS DSRHR-3-9 20 SS DRHR 21 20 SS DRHR-3-22 20 SS DSRHR-3-10 20 SS DSRHR-3-11 20 SS DRHR-3-23 20 SS TRHR-3-191 20 CS to SS TRHR-3-192 20 CS TRHR-3-193 20 CS TRHR-3-194 20 CS DHS-3-1 6 SS DSHS-3-1 6 SS DSHS-3-1A 6 SS DSHS-3-2 6 SS DSHS-3<<3 6 SS DSHS-3-4 6 SS DSHS-3-5 6 SS DHS-3-2 6 SS DSHS-3-6 6 SS DSHS<<3>>7 6 SS DSHS-3-8 6 SS DHS-3-3 6 SS DSHS-3-9 6 SS DSHS-3-10 6 SS DSHS-3-11 6 SS DRHR-3-3 24 SS DRHR-3W 24 SS DSRHR-3-1 24 SS DSRHR-3-2 24 SS DRHR-3-5 24 SS DRHR-3-6 24 SS D SRHR-3-3 24 SS DSRHR-3-4 24 SS DSRHR-3-4A 24 SS DRHR-3-7 2'4 SS DRHR-3-8 24 SS DRHR-3-9 24 SS DRHR-3-12 24 SS DRHR-3-13 24 SS DSRHR-3-5 24 SS DSRHR-3-5A 24 SS DRHR-3-14 24 SS DRHR-3-15 24 SS DSRHR-3-6 24 SS DSRHR-3>>7 24 SS DRHR-3-16 24 SS DRHR-3-17 24 SS DRHR-3-18 24 . SS DRHR-3-19 " 20 SS
BFNP Sl'.6.G Page 262 SEP 29 1981 DPP Assigned Sizes Veld No. inches Material DSHS-3<<12 6 SS DSHS-3-13 6 SS DSHS-3-14 6 SS DSHS-3-15 6 SS DHS-3-4 6 SS DHS-3-5 6 SS DSHS-3-16 6 SS DSHS-3-19 6 SS DHS-3-6 6 SS DHS-3-7 6 CS to SS TRHR-3-455E 6 CS TRHR-3&55C 6 CS TRHR-3<<455A 6 CS TRHR-3-455D 6 CS
NSB NSA 240~ I20~
DC53 IB OCS.3 9 DSC5.3 13 DSCS-3 6 6IB'lyL
'CS EL OCS-3 I7 0 CS.3.8 3- l6 VALVE VALVE l4B I4A OCS3.7 I
~
DcC,5 12 PSC5.3 II
~
~OI Mg
'CI CA ISI OSC53 5 RI DSCS 3.4 aO I" 0'A DSCS-3 I DSC5-3-3 DC53 IS OC53 6 CX)
DC5.3-I4 CQ OSCS 3.9 VA'E VALVE DC53 5 l3B l3A I
VALVE VALVE OSCAR.3 2 I IBB l2h EL 605 7'h EL 6OS'4."
IIIII I
illII O<C'c.3 - 7 OSCS I OCS-3 3 DCS-3-0 DC -3 4 REF. OWGS.
DCS-3. I2 TVA 47KI772 TVA 47W335-IS ORAVO E2456IC-34 REVI5ION NOTES:
ORAVO E24 56IC-3 5 O INDICATES PIECE NUMBER OXCS -N-N t'
D SDRAVO FIELD WELD DS=DRAVO SHOP WELD waco eo.
~
SCev<CSSCC VALLCy AUyteOalTy 00 ryeSS PSOyyISOsl WEI.O IDENTIFICATION UNIT NO, CORE SPRAT SYSTEM BROWNS FERRY NUCLEAR PLANT
. ~~+-.:.-lmeizw
BFNP SI 4.6.G Page 264 SEP29 1981 CORE SPRAY SYSTEM BROWNS FERRY NUCLEAR PLANT UNIT 3 DPP Assigned Size Weld No. ~(Inches Material TCS-3-401 10 CS to SS nozzle to safe end TSCS-3-402 10 CS to SS TCS-3-403 10 CS TSCS-3-404 10 TCS-3-405 12 CS to SS 12 CS to SS TCS-3-406'CS-3-407 12 CS TSCS-3-408 12 CS TSCS-3-409 12 CS TCS-3-410 12 CS to SS TCS-3-417 10 CS to SS nozzle to safe end TSCS-3-418 )0 CS to SS TCS-3-419 10 CS TSCS-3-420 10 CS
.TCS-3-421 12 CS to SS TCS-3-422 12 CS to SS TSCS-3-423 12 CS TCS-3-424 12 CS TSCS-3-425 12 CS to SS TCS-3-426 12 CS
BFNP SI 4.6eG Page 265 SE~<9 ~98>
CORE SPRAY SYSTEM BROMNS FERRY NUCLEAR PLANT UNIT 3 DPP Assigned Size Meld No. ~(Inches Material DCS-3-14 12 SS DSCS-3-9 12 SS DSCS-3-7 12 SS DCS-3-13 SS DCS-3-12 12 SS DCS-3-5 12 SS DSCS-3-2 12 SS DSCS-3-1 12 SS DCS-3-4 12 SS DCS-3-3 12 SS Reference Drawings:
TVA 47K1772 TVA 47M335-15 DRAVO E24561C-34 DRAVO E24561C-35
RCRO 3- 49 RCRD 48 c RCRO-5-43 PCRDS I N9 RCRD-3 -45 14 6' CA TO 4 RCRD- 5 - 4T P1 f5wv)w REDUCER M IT/
F LO W 00 I 0 C'W RCROS-3 -5 6 TO 4" REDUCER RCRD -5. 46 M Ch
'RCRO-3-44 RCRDS-5-2 & r)
O Q3 Rx8 c 8 TEE CL3 RCRO 5 40 CONT, FR'5M CIIQ 2 I 44 C REVISION NOTES I. REROUTE CRD RETURN LINE AtWAIW ~
tcseoeccccc recce sanmsnv WELD IDENT IF I CATION tONVCllW CRD HYDRAULIC RETUPN I.INE 8ROWNS FERRY NUCLEAR PLANT
~e chal Gill 2lh
BFNP'Z 4.6.a Page 267
~EP 28 1981 DPP Assigned Sizes Meld No. ~{Inches Material RCRD-3-1 CS RCRD-3-3 CS RCRD<<3-2 CS RCRD-3-43 4 CS RCRD-3-44 CS RCRD-3-45 RCRD-3-46 CS RCRD-3-47 CS RCRD-3-48 CS RCRD-3-49 CS to SS
DRWC3 SB D5RWC-3-7 ORWC 3'4 IlllI 607 6
) Elll I Ill ORWC 3-56 DSRWC 6 DSRIYC 3-9 DRWC-3-5A DSRVK-3 5 EL 578 9 8" TO 4 REDUCER RCRD-3-43 8358346 T EE DSRYrC-3-4 ~E 574 5.
~ RCRD-3-45 6 TD 4 REDUCER 24 FEEOWATER ~~CCIIC ~ 4 DSRWC-3 3 n 547 CCIIWC.3.3 ON CHQ 2I43.C EL. 57l 7374 DRVVC-3 59 DRWC-3 59 A DRWC-3 DRWC 59 8 OSRYC3 2 60'RCIC-3.2 7 5 ORWC3 3 ORYK-3 2 CA DSRWC I DRWC I i EL. 586 3 TRCIC-3 5 KL. 567 0 tU CA bI DS RWC-3. IA 00 A DRWC 3'IA REF. DwC5. TRCIC-3.6 T RC I C-3-7 OO TVA 47W335-I4 TVA 47W335-I7 TYA 4 7 KI776 DRAVO 2456XC-49 REVISION . NOTES:
20 RHR DRAVO 2460IC-40 I ADD CRD THERMAL MIXING TEK 0 INDICATE5 PIECE NUMBER TRCIC-N N I TVA I UNIT NO Wao Na DS= DRAYO 5HOP WELD
~ Chhf55EC VALECV *333740+773 REACTOR WATER CLEAN UP ~ 747IDI tt tt735 t44444(3344 II REACTOR CORK WELD IDENTIFICATION ISOLA'TION COOLINC REACTOR WATER CLEAN UP AK) RCK
'BROWNE FERRY NUCLEAR PLANT I'EI-4:I44 C
BFNP SI 4.6.G Page 269 DPP Assigned Sizes Weld No. Inches. Material SEF'sr ass>
DRWC-3-1A 6 SS DRWC-3-1 6 SS DSRWC-3-1 6' SS DRWC-3-2 SS DRWC-3-3 6 SS DSRWC-3-JA 6 SS DSRWC-3-2 6 SS DSRWC-3-3 6 SS DSRWC-3A 6 SS DSRWCM-5 6 SS DSRWC-3-6 6 SS DSRWC-3-7 6 SS DRWC-3-4 6 SS DRWC-3-5A 6 SS DRWC-3-5B 6 SS
- DRWC- 3-60 8 CS
- DRWC- 8 CS DSRWC-3-8 4 CS DSRWC-3 Ij CS DRWC-3-58 4 CS TRCIC-3-7 6 CS TRCIC-3-6 6 CS TRCIC-3-5 6 CS TRCIC-3 2 6 CS DRWC-3<<59A CS DRWC-3-59B 4 CS
26 MAIN STEALI THPQ-3 66 THPCI-3-67 THPCI-3-66 THPC I 69 35 THPCI-3-70 THPCI-3.70 8 24 FEEOWATER ~E. 57 5 THPCI-3-7OA THPCI 3 TI THPCI 3-65 I5 I THPCI 3 72 THPCI 3 64 I3 67 THPCI-3-73 THPCI 3 62 THPCI-3 6I THPCI 3 738~ THPCI-3 73A THPCI-3-73E CA CO OI REF. OWGS: Q 7vA 47W335. 12 Q 00e C'O TVA 4 7W335- II THPCI-3-73G TVA 47K f567 wo 0 INDICATES PIECE NIMBER 0 C3 CO W LO NO UNIT NO.
HIGH INJFCT ION PRESSURE'OOLANT W
~
Tflellt55CC VALlCT AMtHOal1Y K &+tt +WOVCTIOII LD IDL NTIFICATION-HIGH PRESSURE COOI.ANT INJECTION BROWIIS FERRY NUCLEAR PLAHT
BFNP SI 4.'6".G 271 'age SEP 29 1981 DPP Assigned Sizes Weld No. Inches Material THPCl-3-61 14 CS THPCI-3-62 14 CS THPCI-3-64 14 CS THPCX-3-65 16 CS THPCI-3-66 10 CS THPCI-3-67 10 CS THPCI-3-68 10 CS THPCX-3-69 10 CS THPCI-3-70 10 CS THPCI-3-70A 10 CS THP CI-3-71 10 CS THPCI-3-72 10 CS THPCI-3-73 10 CS THPCI-3-70B 10 CS
.THPCI-3-73A 10 CS THPCI-3-73B 10 CS THPCX-3-73E lo CS THPCI>>3-73G 10 CS
g6 TO TURt9NE STOP VALVES OSMS 3 4 ningcP IO gb TSIS DSMS-5 26 5-I9 0+
CONT OH CH M 2405 C OMS 3 2OF2 N N j6 DSMS 3-27
.t DSMS 3-28 I8 ~4 OSMS 5 22 OT$ N IA DMS 3120 O IO III 24'XI8 C~
RE 4
~
eo c'e OSMS 3 29 Fz4 OSMS-5-34 DSMS 24 alS'GXKOI tTTRCLO~
OMS 34 2 DMS-3 IT OSMS 3 33 OSMS 5 I t'ag
/ 8Tj DMS 3 I8 DSMS-3 2I O
~ V OSMS 5-I4 DMS-3 3
.f. Pl weeM w CODE CLASS 2 OSMS-5-IO Ã At.t. CARBON STEEL, ~80 14 OSMS-3 9 ~ II DMS 3 2 MA OSMS 3 IY Q3 OO DSMS-5 5 I8 6+6 II4 I:II g,$ , ~.6~
4LE 0
DMS-3-t4 DQ6 3-I5 OSMS 3 I OMS 5t ycI g4 g ~et FCV I IS 06+
0~.9 a4
+0 e~
DSMS 3 8 OL1 t OOICF lI(OUQC $ 1Z T(1 NCLSLC TaLLLT A4IHO1IIT
~ teOI V TVI~ IIIIILT4T REF OWGS. ~
8FNP FROM CH M 2I40-C ORAVO E. 24~Cd MAIN STEAM DSMS 3 4 TVA 4TWSM-I 26 X 24 ECCENTRIC REDUCER LE 9450695 UNIT OMS 5 I3 FCV.I 52 V4. " ') QN 2405'C
OSAS-25 DSAS-24 6"x4 CONC.
REDUCER DSAS-20 OSAS-26 DSAS -2I~ FCV I- I4I 6" x4" CONC REDUCER OSAS-l6 DSAS~
FCY I-l33 TO REP TURBINE C ~ DAS-l6
~DSAS-23 OSAS-I7 6" a 6"x3"REDUCER TO RFP.
8'x 4"CONC. y-DAS-II REDUCER OSAS IB TURBINE 8 OS AS-l9 y 6DSAS-l4 STRTEE FCV I-!25- 6 DSAS-l3 DSAS-l2A TO RFP TURBINE A ~ GAS-6 DSAS45 DSAS-l2 6 STR. TEE DAS-IO OSAS-ID~
OSAS-9 ~ DAS-5 DSAS-I I DSA S-8~ 6"STR. TE E OAS-4 DSAS-7 DAS-3 DSAS-6 Cn
~DSAS-5 Pl dco td 4 My o ww M~
BOAS-2 mA CH- M 2405-C CO FROM I OF 2 DSAS-4 CODE CLASS 2 ALL CARBONSTEELSCH.80
~ OSAS-3
!8 MAINSTEAM HEADER DSAS-2 I I REF DWGS: TCNHt\SCC VALLCY AWNORITT I Wvh44 & ~O tKOVCMA DRAVO E-2460-IC 5 DSAS-I BFNP AS-I 18" x 6" SWEEPOLET AUX. STEAM D
sD
- I fl
TRHR-3-Zll TRHR.J.Z54 TRHR J 2IO TRHR-3-l9SA F FIIRII CR.II RI~ I.C TRHR 3 235 V 2 OF 2 TRHR-3-209 TRHR-3-66 FCV-74-47 TRHR- J 236 TRHR 3 208 FCV-74-2 TRHR 3 207 TRHR 3 l9$
749 TRIIR-3 206A TRHR 3 l97 TRHR 3 Z57 FROM 24 COIDENSATE Taut 3 257A 8/8 TRHR-3 206 HEADER R ~SIATCH SlAtC9I gpE A TRHR-3 Zi 3 LINK C~ RHR-3 2I4 <<NCV 74 4S TRHR 3 ZIB TRHR-3 l96 TR tttttR 5 SI9
~ I TRHR 3 238
/
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/ TRHR 3-202 TRHR-3 I99 l TRHR 3 229 <<'ttt99R 5 SI8A TRHR-3-200 TNtft 5 SNI
<<Ttttft 5'SI7
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-C ZOF+ CONT ON CH M 2406 C TRHR 3 203
~YIINR 3 35 TRift 9'3 a BIIILBIItdKC 2 OF 4 TRHR-3-262 CVQR 1 TRHR 3 3ll TRHR-3 263A TRHR 3'32 TRHR 5 SISA TRKI-3-244 7RHR 3-245 TRHR-3 9943 J
TRHR-3-263 TRHR-3 264 NATCH LINE E IIATCH LINK F 9SI TRHR 3-26$
TRHR-3 23l
~78998 5 246 TRHR-3 230 TRHR-3 266 FCV 74 I TRHR 3 267 TRHR-3 268 TRHR 3 ZZI TRHR 3 30$
TRHR-3-269 FCV 74 2S TRHR-3 270 FROM. RtAI HEADER FCV 9S'~~ A W 4 FCV 74 97 TRHR 3 304 TCH UNK KRR TRHR 3 27I TIINR-9426~ "7
<<TRHR 5'427 <<-Tpttt SWK TRHR 3272 A TRISI 3 4IS TRHR 3 303
<<.TRNA S 428 If R 4 Tittft 94I4 999 O FCV 74-36 TRtft.3.48 A 4 TIIIN-5.429 ~TNft-3-4IS iR O TRHR 3-273 TRHR-5 452 TIIIIR 3AM ~TIINII5 45A Cll TRHR 3 275 TRHR 3 302
<<-TAIN 3<It TRHR 3 30IA
~TCII LII8: f 0 ttt OI ol M HEADER Ft I A KH LNE C 99
<<TIINII5<09 TRItt 5.408 TRHR-3 JO O+ RT TRHR 3-3ll TRHR 3 276 ID C g
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4 20 QILX 875 NOAL WALL THILFCB.
l6 QQX 9375 NOM, WALLTHICt'.S.
TRNR Titift.3'295~ 3296~ CS cia l4" QO. X 375 NOMR WALL THICC.S.
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TA4328I~~
CONT ON CH M-2406-C 2 OF+
+II8ft5 253 TRHR 3 279 TRHR 3 278 F
TCFIFICSSCC VACCCT AU999OAICT
~TIINR 3 252 REF. OWG. I ~ FRIIRFR SF 99999 9999RCFIFR IIAICH UNE A BFNP
<ICAtOI uNE TVA 47W335 4 RHR SHUTDOWN SVPPLV UNIT 3 F
TRNA 3 183F TRHR 3 185E <<TRI41 3897 ZCXZO REO. Et.L.
TAHR 5-1830 TRHA 5 64A 24 x 20 REO ELL TRHR 3 64 TRHA-5.648 TRNA-3-178 ~O TRIS-3 64C TRHR-3-183C TRHR 3 179 TRHR 3580
+0
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)O 4l nl ccl g
o Cc5.
p$ n R
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IS58 IRICI 3 A~~+g 402~
~MR 3~
~T R N.5.596 TRHR
~tact-5-g99 3 d
cv n n
Oc n
ag 9%0. I cc
~ TRHR 5 54 ct'O CV 74 22 TRICI 340M w ~TRRR.SM TRHR 3 185A TRHR-3 56 0
TRHR 3 359 TRHR 5 338 cu IC EV I
&n nn <
nnn I
~
CCc
~
CC X
CC I
fl WC t
h+
ccc I ~TRNA-3 182 TRHR-3-183 TRHR-3 58 24'X 20 REO.
'P ELL, TRHR 3 HCV 74 33
~TRHR 3 589 TAIS 5-357 CL CC TRHR-3 356 n TRHR 3-181 TRHR-5 575 TAIS 3 52 I 0 5-51 x
CC TRHR 3-388 TRHR 3-535 nn 24 X 20 REtLELt ccl TRHR CV ICI CC I TAHR 387 TRHR 5 334 n TRHR-3 170 CC <<TRHR 3 386 cx TRHR 3-374 x 0cv Z 0 I YRHR 3 385 7RHR 5 169 TRHR 3 375 YRHR 3 60 TRHR-5 355 V TRHR-3 332 YRHR 5-372 clc 7RHR 5 59 TRHR 3 3848 TAHA-3 331 O TRHR 3 330, cc gI TRHR 3 371 TRHA 3-48 ORIFICE t
TRHR 3 529 I I CV ~
I I OINT A 'TRHR-5 584A CONT ON CH~2406-C TRHR 3 37C8 TRHR-5-3498 RHR 3 OF '4 TRHA-5'570A TRNA 5 328 ~TRIS-3-549A 4 >oOn Z
I I TRHR-3-349 R O KgCC TI862-3-47 TRHR 5 5278 ORIFICE TRHR-3 348 OK p TRHR 3 584 TRHR-5 347 TRHR 3 370 TRHR-3-382 i j T)HA.5.327 TRHR 3 546 TAHR 3-581 TRHR 3 583 I
I TRHR 3345 TRHR 5
! i ~ Clc
( g 4 ccc TRHR 3 319 TPHR 3 327 TRHR 3-344 TRNA 5 326 74-559 24'GD.X 40tf NOALWALL YHK.cCS n TRIS-5 365
'RHA L. 4I J 74 559C a.'RIA X
5 366 cc I
~
cc:
?
z cc 2(POD.X SOO'NOM.WALL TIIK.,CS.
3 325 TRHA 5 324 0 C6 TRHR 3 578 IS GQ,X SOIFNOM.WALL TPP,CS.
IS n I TRIIR 5'577 IO'ttDX465 NOMWA&QI i
t 74 559A- O ~
cc ICI TRHR 5 545 n 74%598 20 XIS REO Pl P 5
O 0cc 5
~TRHR 3 342 cx X ELL.
Q ~
TRHR-3 325 ea TRHR 3 541 CC:
I TRHR-5 368 N
TRNA 3 540 TRHR-5 565 P I TRHR-3-376 TRHR-5 321 TRIS 5 322
~ FROM CH M 2406-C TRHR 3 36Z 2406 C I OF4~ CCCCCCC15CC VhllCT AUNOONII~
0 XIS"AEONS I OF 4 ZIF X 18 REL ELL. Siaao cl tee< ~ raWCCOr i ELL.
FROM CH-M 2408C cc.. SFNP I OF 4 YRHR 5 360 RHR SHtiTOOWN SVPPIY TRHR-3 320 RHR PUMP 8 UNIT- 3 I REF. OWS. I IRHR PUMP A RHR PUMP C TVA 47W335 7 l~~ --- DHI 2406 .C
~CONT T
g Z IL IC Z l Ig I
PONT A CONT ON CH%-2406-C PHR 2 OF +
TRHR 3 168 CC g
I IC Z
TRHR 3 98 TRHR 0
A 3%6 IC I
TRHR-3 150 TRHR-3 97 TRHR-3 106 0
n g t
-/
/
FCV TRHR8058 CTRMR-3 105A LTRHR.3~
74<7 TO TORUS SPRAY TRHR 3 19
~r ~FCV 74 53 DRHR 3 2 DRHR-3-1 CONT ON CH N 214I C I OF 2 TRHR 3 TRMR-3 27 TRHR 3 26 TRHR-3-445 TRIN 3vI46 TRMR TRHR 3 436
~
TRHR 3-447 TRMR 3 448
. TRHR.3-437 3935 IS'X 6 RED+
TRHR 3 434
~~l l
-~n
+
I I
'IRMI -3.30 TRHR-3-29 TRHR 3 28A TRHR-3 TRHR 3 444 443 TRHR-3 442A FCV 78 61 TO FUEL POOLCOOLING RHR i
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APPENDIX B - UNIT gl, 40-MONTH CYCLE EXAM CALIBRATION DRAWING REQUEST
-METHOD PROCEDURES BLOCKS NUMBER FOR RELIEF OUTAGE; REMARKS RPV Circ. ISI-2 RPV Long. ISI-2 Closure Head Seam (RCH-l-,lC) BF-UT-8 BF-llC Dec. 78; Stud 821-23, .5 ft.
Closure Head Meridional F
UT BF-UT-8 BF-11C Dec. 78; Report R-061 Vessel/Flg. (14") BF-UT-8 BF-10C CHM-992"C Dec. 78; Stud j/12-36
(') NUT<<NC-1A BF-10C CHM-992-C Dec. 75; Stud i/1-12 Head/Flg. (14") UT BF-UT-8 BF-11C Dec. 78; Stud ij13-34 (7') UT NUT-NC-1A BF-llC Dec. 75; Stud gl-12 l
Main Steam (N3D) UT ~ BF-UT"8 BF-10C CHM-1089-C Dec. 78; Nozzle/Vessel Nozzle ~
(26") UT BF-UT-5 BF-10C Dec. 78; Inner Radius jSafe End. UT , BF"UT-8 BF-9C Dec. 78 Core Spray UT BF-UT-8 BF-10C CHM"1089-C Dec. 78; Nozzle/Vessel Nozzle 'N5A-10") UT BF-UT-5 BF-10C Dec. 78; Inner Radius Safe End UT BF<<UT-8 BF-6S Dec. 78 Feedwater ",
UT NUT-NC-lA BF-llC CHM-992"C Dec. 75; Nozzle/Vessel Nozzle ~
(N4F-12") UT NUT-NC-1A BF-llC Dec. 75; Inner Radius Safe End' UT NUT-NC<<lA BF-15C Dec. 75 Fee)water Nozzle ( >
)
Safe End Cn l
Pl Q CA Dec. 75; Nozzle/Vessel~ 0" ~ ~~
F$
Recirculation UT NUT-NC-1A BF-11C CHM-992"C Out)et (NlA-28")
Safe End UT UT NUT-NC-lE NUT-NC-1A BF-11C BF"9C CHM-1081-C Dec. 75; Inner Radius Dec. 75
~ o ~ ~
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APPENDIX B - UNIT gl, 40"MONTH CYCLE EXAM CALIBRATION DRAWING REQUEST METHOD PROCEDURES BLOCK NUMBER FOR RELIEF OUTAGE; REKQKS Recirculation UT NUT-NC-1A BF-11C CHM-992-C Dec. 75; Nozzle/Vessel Inlet (N2E-12") UT NUT-NC-1C BF-11C Dec. 75; Inner Radius Safe End NUT-NC-lA BF-6S CHM-992-C Dec. 75 PT NPT-NC-1 N/A (N2G-12") UT BF-UT-8 BF"llC CHM-1081-C Dec. 78; Nozzle/Vessel UT BF-UT-5 BF-11C Dec. 78; Inner Radius UT BF-UT-8 BF-6S CHM-1081-C Dec. 78 PT BF-PT-1 N/A Head Instrument Nozzle (
Closure Nuts (10) UT BFNP-A BF-13 8 1219 Dec. 75; jjl-10 (20) UT BFNP-A BF-13 8 1219 Dec. 78; Oil-30 (10) VT Visual fjl N/A Dec. 75; jjl-10 (20) VT ~ Visual $/1 N/A Dec. 78; Ill-30 Closure Studs (7) BFNP"A BF-13 8 1219 Dec. 75; /jl,31,46,54, I 61,76 8 83 (23) BFNP"A BF-13 6 1219 Dec. 78; g2-24 (7) Visual gl N/A Dec. 75; g1,31,46,54, 61,76 8 83 (23) Visual f/1 N/A Dec. 78; Ij2"24 Closure Washers (30) Visual jjl N/A . Dec. 78; gl-30 Closure Bushings (4) Visual 01 N/A Dec. 78; Ij68-71 Ligaments (24) BF"UT-4 N/A Dec. 78 (6) NUT-NC"1B BF-11C Dec. 75 Clad Patch (2) N-VT-1 N/A Dec. 78 Vr &
MW oo iD C Support Skirt BF-UT-8 BF-12C CHM-1091-C ISI-3 Dec. 78 CD o mA
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APPENDIX B - UNIT gl, 40-MONTH CYCLE EXAM CALIBRATION DRAWING REQUEST METHOD PROCEDURES BLOCKS NUMBER FOR RELIEF OUTAGE; REMARKS GR-1-28 (28") UT BF-UT-8 BF-8S CHM>>1081-C Dec. 78 KR-1-24 (28") UT BF-UT-8 BF-SS CHM-1081-C Dec. 78 GR-1-53 (28") UT NUT-NC- lA BF-SS CHM-1081-C Dec. 75 GR-1-26 (22") UT NUT-NC- lA BF-8S CHM-10Sl-C Feb. 75 GR-1-20 (12") UT BF"UT-8 BF-6S CHM-1081-C Dec. 78 GR-1-14 (12") UT BF-UT-8 BF-6S CHM-1081-C Dec. 78 GR-1-43 (12") UT BF-UT-8 BF-6S CHM-1081-C Dec. 78 I
KMS-1-30,(26") UT BF-UT-S BF-9C CHM-1082-C Dec. 78 GMS-1-12 (26") UT BF-UT-8 BF-9C CHM-1082-C Dec. 78 Q{S-1-15 (26") UT BF-UT-8 BF-9C CHM-1082-C Dec. 78, Pipe Whip GMS-1-24 (26") UT BF-UT-8 BF-9C CHM-1082-C Dec. 78, Pipe Whip GMS-1-32 (26") UT NUT-NC-lA BF-9C CHM-1082-C Dec. 75 Pipe Whip KMS-1-59 (6") UT BF-UT-8 BF-3C CHM-1082-C Dec. 78 KMS-1-60 (6") UT BF-UT-8 BF-3C CHM-1082-C Dec. 78
=-
KMS-1-36 (6") UT BF-UT-8 BF-3C CHM-1082-C Dec. 78 KMS-1-102 (6") UT NUT-NC-lA BF-3C CHM-1082-C Dec. 75 KMS-1-53 (10's) UT NUT-NC-1A BF-9C CHM-10S2-C Dec. 75 j Branch Conn.
I I KFW-.1-8 (24") UT 'UT-NC-lA BF-9C CHM-1080-C Dec. 75 KFW-1-9 (24") UT BF-UT-8 BF-9C CHM-1080-C Dec. 78 KFW-,1-10 (20") UT BF-UT-8 BF-9C CHM-1080-C Dec. 78 GFW l-ll (12") UT NUT-NC-lA BF-5C CHM-1080-C Dec. 75 KFW 1
~
38 ( 1 2 ) UT BF-UT-8 BF-5C CHM-1080-C Dec. 78, Pipe Whip KFW.1-39 (12") UT NUT-NC-lA BF-5C CHM-1080-C Dec. 75, Pipe Whip I
DSCS-1-5 (12") UT N-UT-1 BF-6S CHM-1089-C Jan. 80 DSCS-1-12 (12") UT N-UT-1 BF-6S CHM-1089-C Jan. 80, Pipe Whip DRHR-1-13 (24") NUT-NC-1A BF-SS CHM-1088-C Feb. 75 DSRHR-1-7 (24") NUT-NC-lA BF-8S CHM-1088-C Feb. 75, Pipe Whip DRHR-1-21 (20") NUT-NC-lA BF-SS CHM-1088-C Feb. 75 Pl NPT-NC-1 '0 Vr' I
N/A 0 TRHk-1-190 (20") NUT-NC-IA BF-9C CHM-1088"C Dec. 75, Di Ssl mi lar OQ O 4 DSHS-1-14 (6") BF-UT-8 BF-4S CHM-10SS"C Dec. 78 DSHS-1-19 (6") NUT-NC-lA BF-4S CHM-108&"C Feb. 75 0
APPENDIX B - UNIT foal, 40-MONTH CYCLE EXAM CALIBRATION DRAWING REQUEST METHOD PROCEDURES BLOCKS NUMBER FOR RELIEF OUTAGE; REMARKS RCRDS-1-3 (8") N-UT-1 BF-3C CHM-1097-C Jan. 80 RCRDS-1-2 (6") N-UT-1 BF"3C CHM-1097-C Jan. 80
'RCRD-1-43 (4") N-UT"10 BF-27C CHM-1098-C Jan. 80 RCRD-1-46 (4") N-UT-10 BF-27C CHM-1098"C Jan. 80 DSRWC-1-4 (6") N-UT-1 BF-4S CHM-1098-C Jan. 80, Pipe Whip DSRWC"1-7 (6s') N-UT"1 BF-4S CHM-1098-C Jan. 80 THPCI-1-148 (10") UT NUT-NC-lA BF-5C CHM-1099"C Dec. 75 THPCI-1-154 (10") UT NUT"NC-lA BF-5C CHM"1099"C Dec. 75, Pipe Whip ZR-1-23 (4") NUT-NC-1A BF-6S CHM-1081-C Feb. 75, Branch Conn.
KR-1"32 (4") NUT-NC-lA BF-2S CHM-1081-C Feb. 75 KMS-1-63 -(3") NUT-NC-lA BF-9C CHM-1082-C Dec. 75, Branch Conn.
~
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APPENDIX B - UNIT g2, 40-MONTH CYCLE
. EXAM CALIBRATION DRAWING REQUEST METHOD PROCEDURES BLOCKS NUMBER FOR RELIEF OUTAGE; REMARKS RPV Circ.
C-4-5 UT , N-'UT-9 BF"18C CHM-2046-C ISI-2 Sept. 80 RPV I,ong.
.V"3 "A N-UT-9 BF"18C CHM"2046-C ISI-2 Sept. 80 Closure Head Seam (RCH-2-1C) BF-UT-8 BF"11C May 78; .5 ft. Clockwise from RCH"2-4V I
Closure Head
.Meridional (RCH-2-4V)
I UT BF-UT-8 BF-11C May 78 Vessel/Flg. UT BF-UT-8 BF-10C May 78; Stud fj8-38 I
Head/Flg.. UT BF-UT-8 BF-llC May 78; Stud 9 34-62 Mdin Steam UT BF-UT-8 BF-11C CHM-2046"C May 78; Nozzle/Vessel Nozzle (N3D-26") UT I '
BF-UT-5 BF-11C May 78; Inner Radius Safe End UT BF-UT-8 BF"9C May 78 I
Core Spray'ozzle
( )
Safe End I
Feelwater N-UT-9 BF-18C CHM-1094-C Sept. 80; Nozzle/Vessel (N4A-12")
.'ozzle N-UT-2 BF-18C Sept. 80; Inner Radius Safe End N-UT-1 BF-15C Sept. 80 Feehwater UT N-UT-9 BF-18C CHM-1094-A Sept. 80; Nozzle/Vessel (N4F-12")
- 'ozzle UT N-UT-2 BF-18C Sept. 80; Inner Radius CO Safe End,- UT N-UT-1 BF-15C Sept. 80 P1 I Q %ICAL H%
I Reck rcula t'ion UT N-UT-9 BF-18C CHM-2046"C Sept. 80; Nozzle/Vesse$ e ~w Outlet (N1A-28") UT N-UT"2 BF-18C Sept. 80; Inner Radius ~ a Safe End UT N-UT-1 BF-8S Sept. 80 PT N-PT-1 N/A Sept. 80
APPENDIX B - UNIT g2) 40-MONTH CYCLE EXAM CALIBRATION DRAWING REQUEST METHOD PROCEDURES BLOCKS NUMBER FOR RELIEF OUTAGE; REMARKS Recirculation BF-UT-8 BF-11C CHM"2046-C May 78; Nozzle/Vessel Inlet (N2B-12") BF-UT-8 BF-11C May 78; Inner Radius Safe End N-UT-1 BF-15C Sept. &0 N-PT-1 N/A Sept. &0 Recirculation Inlet ( )
Safe End Recirculation Inlet ( )
Safe End Jet Pump (N8A) N-UT-9 BF-18C CHM-2046-C Sept. 80
{4ll) N-UT-2 BF-l&C CHM-1094-A Sept. 80 Safe End N-UT-1 SQ-13 CHM-1094-A Sept. 80 CA N-PT-1 N/A CHM-2046-C Sept. 80 Pl MM H .~
00 e
Head Instr. (N6A2) UT I N-UT-9 BF-19C CHM-1094"A Sept. 80, Noz/Ves (6tt) UT '-UT-2 BF-19C CHM-1094-A Sept. 80, Inner Radius 4J Noz/Flg UT N-UT-1 BF-30C CHM-1094-A Sept. 80 QD Co Ligaments BF-UT-4 N/A May 78, Studs Pj&-jj3&
Support Skirt N-UT-7 BF-12C CHM-1091-A ISI-3 -Sept. 80 Closure Studs UT BFNP-A BF-13 May 78, Stud f/&, 10, 12, 14, 16, VT Visual j/1 N/A 207 26> 28> 30'2> 34> 36~ 38 40, 42, 44, 46, 52, 54, 56, 58, 60~ 62) 64~ 66~ 68> 70) 727 90 92 Closure Nuts BFNP-A BF-13 May 78, Nut f/I-g6, 22, 27, 28, (Nuts 6 Washers) Visual g1 N/A 39-49, 60, 63, 65, 67-73 Closure Bushing Visual 7/1 N/A Bushings 822-25 Clad Patch Visual g2 N/A 4th Pad down from Flange 9 30 2nd.Pad down from Flange g 210~
APPENDIX B - UNIT g2, 40-MONTH CYCLE EXAM CALIBRATION DRAWING REQUEST METHOD PROCEDURES BLOCKS NUMBER FOR RELIEF OUTAGE; REMARKS GR-2-27 (28") UT BF-UT-8 BF-8S CHM-2068-C May 78 KR-2-24 (28") UT BF-UT-8 BF-8S CHM-2068-C May 78 GR-2-53 (28") UT BF-UT-8 BF-8S CHM-2068-C May 78 GR-2-18 '(22") UT N-UT-1 BF-8S CHM-2068"C Sept. 80 GR-2-47 (12") UT BF-UT-8 BF-'6S CHM-2068-C May 78 GR-2-37 (12") UT BF"UT-8 BF-6S CHM-2068-C May 78
, GR-2-40 (12") UT BF"UT-8 BF-6S CHM-2068-C May 78 GR-2-7X (4") UT NUT-NC-lA BF-2S CHM-2068-C May 76 GR-2-30X (4") UT NUT-NC-1A BF-2S CHM-2068-C May 76 KR-2<<19 (12n) UT N-UT-1 BF-8S CHM-2068-C Sept. 80, Branch Conn.
KMS-2-30 (26") UT BF-UT-8 BF-9C CHM-2069-C May 78 GMS-2-12 (26") UT BF-UT-8 BF-9C CHM"2069-C May -78 GAS-2-15 (26") UT BF"UT"8 BF"9C CHM"2069-C May 78, Pipe Whip GMS"2-24 (26") UT BF-UT-8 BF-9C CHM-2069-C May 78, Pipe Whip GMS-2-32 (26") UT BF-UT-8 BF-9C CHM-2069-C May 78, Pipe Whip KHS-2-36 (6") UT BF-UT-8 BF-3C CHM-2069-C May 78 KMS-2-37 (6") UT BF-UT-8 BF-3C CHM-2069-C May 78 KMS-.2-59 (6") UT BF-UT-8 BF-3C CHM-2069-C May 78 KMS-2-60 (6") UT BF-UT-8 BF-3C CHM-2069-C May 78 ICONS".2-53 (10") UT N-UT-1 BF-9C CHM-2069-C Sept. 80, Branch Conn.
KMS-2-43 (6") PT N-PT-1 N/A CHM-2069-C Sept. 80, Branch Conn.
KMS-,2-46 (6") PT N-PT-1 N/A CHM"2069-C Sept. 80, Branch Conn.
I KFW-,2-8 (24") UT BF-UT-8 BF-9C CHM"2067-C May 78 KFW-.2-26 (24" ) UT BF-UT"8 BF-9C CHM-2067-C May 78 KFW-'2-10 (20") UT BF-UT-8 BF-9C CHM"2067"C May 78 GFW-2-15 (12") UT BF-UT-8 BF-5C CHM-2067-C May 78, Pipe Whip KFW-2-38 (12") UT BF-UT-8 BF-5C CHM-2067-C May 78, Pipe Whip KFW-2-39 (12'() UT BF-UT-8 BF"5C CHM-2067-C May 78, Pipe Whip TCS-2-422 (12") UT BF-UT-.8 BF-5C CHM-2071-C May 78 TCS;2-409 (12") UT BF-UT-8 BF-5C CHM-2071"C May 78 Cn W CA C)
TCS",2-417 (10") UT BF-UT-8 BF-5C CHM-2071"C May 78 Cl DSRHR-2-4A (24") UT N-UT-l BF-8S CHM-2070"C Sept. 80 00 0
Z DSRHR"2-7 (24") UT BF-UT"8 BF-8S CHM-2070-C May 78, Pipe Whip 4J M DSRHR-2-11'20") UT N-UT-1 BF-8S CHM-2070"C Sept. 80 TRHR-2-191 (20") UT, PT N-UT-1 BF-9C CHM-2070-C Sept. 80, Dissimilar N-PT-1 N/A OO
APPENDIX B - UNIT jg, 40-MONTH CYCLE EXAM CALIBRATION DRAWING REQUEST METHOD PROCEDURES BLOCKS NUMBER FOR RELIEF OUTAGE; DSHS-2-19 (6") N-UT-1 BF-4S CHM"2070-C Sept. 80 DHS-2-6 (6") N-UT>>l BF-4S CHM-2070-C Sept. 80 RCRD-2-43 (4") UT N-UT-1 BF-1C -
CHM"2073"C Sept. 80 RCRD-2-40 (4") UT BF-UT-8 BF-2S CHM-2073-C May 78, Cap Weld RCRDS-2-2 (6") UT N-UT-l BF-30C CHM-2072-C Sept. 80 PT N-PT-1 N/A RCRDS-2-3 (8") UT N-UT-1 BF-5C CHM-2072-C Sept. 80 DRWC-2-59 (8") N-UT-1 BF-5C CHM-2073-C'HM-2073-C Sept. 80 DSRWC-2-4 (6") BF-UT-8 BF-4S May 78 TRCIC-2-2 (6") N-UT-1 BF-30C CHM-2073-C Sept. 80 THPCI-2-65 (16") N-UT-1 BF>>7C CHM"2074-C Sept. 80 THPCI-2-72 (10") BF-UT-8 BF-5C CHM-2074-C May 78 Recirc. (2A) N-UT-5 BF-13 CHM-2086-C Studs gl-fj5 Pump Studs (2B) N-UT-5 BF-13 CHM-2086-C Studs jjl-jj5 RHR-2-H10 N-VT-4 N/A CHM-2084-C Sept. 80 HS-2-Hll N-VT-4 N/A CHM-2084"C Sept. 80 HS-2-R73 N-VT-4 N/A CHM-2084-C Sept. 80 HS-2-R72 N-VT-4 N/A CHM-2084-C Sept. 80 CS-2-H6 N-VT-4 N/A CHM-2089-C Sept. 80 CS-2-H3 N-VT-4 N/A CHM-2089-C Sept. 80 RWC-2-Hl N-VT-4 N/A CHM-2082-C Sept. 80 FW-2-SSA7 N-VT-4 N/A CHM-2085-C Sept. 80 FW-2-SSA4 N-VT-4 N/A CHM-2085-C Sept. 80 FW-2-H5 N-VT-4 N/A CHM-2085-C Sept. 80 FW-2-SSA3 N-VT-4 N/A CHM-2085-C Sept. 80 FW-2-SSB89 N-VT-4 N/A CHM-2085-C Sept. 80 Cn FW-2-H7 N-VT-4 N/A CHM-2085-C Sept. 80 MS-2-HA2 N-VT-4 N/A CHM-2087-C Sept. 80 e c MS-2-SSA12 N-VT-4 N/A CHM-2087-C Sept. 80 EP M MS-2-HD2 N-VT-4 N/A CHM"2087-C Sept. 80 Vn A MS-2-SSD12 N-VT-4 N/A CHM-2087-C Sept. 80 Q3 N-VT-4 OQ MS-2-HB4 N/A CHM-2087-C Sept. 80
APPENDIX B - UNIT g2, 40-MONTH CYCLE EXAM CALIBRATION DRAWING REQUEST METHOD PROCEDURES BLOCKS NUMBER FOR RELIEF OUTAGE; REMARKS MS"2-SSB6 VT N-VT-4 N/A CHM-2087-C Sept. 80 MS-2-HB1 VT N-VT-4 N/A CHM-2087-C Sept. 80 MS-2-SSB5 VT N-VT-4 N/A CHM-2087-C Sept. 80 MS"2-Hcl VT N-VT-4 N/A CHM-2087-C Sept. 80 MS-2-SSC6 VT N-VT-4 N/A CHM-2087-C Sept. 80 MS-2-SSC1 VT N-VT-4 N/A CHM-2087-C Sept. 80 MS-2-SSC2 VT N-VT-4 N/A CHM-2087-C Sept. 80 MS-2-HC2 VT N-VT-4 N/A CHM-2087-C Sept. 80 R-'2-SS1 VT N-VT-4 N/A CHM-2086-C Sept. 80 R-'2-H3 VT N-VT-4 N/A CHM-2086-C Sept. 80 R-2-H14 VT N-VT-4 N/A CHM-2086-C Sept. 80 R-2-Hl VT N-VT-4 N/A CHM-2086-C Sept. 80 CS-2-H3 MT N-MT-1 N/A CHM"2089-C ISI-9 Sept. 80 CS-2-H6 MT N-MT-1 N/A CHM-2089-C ISI-9 Sept. 80 MS-2-SSB5 MT N-MT-1 N/A CHM-2087-C ISI-9 Sept. 80 Mg-2-HC2 MT N-MT-1 N/A CHM-2087-C ISI-9 Sept. 80 Bl-2-SSA7 MT N-MT-1 N/A CHM"2085-C ISI"9 Sept. 80 MS-2-HCl MT N-MT-I N/A CHM-2087-C ISI"9 Sept. 80 Hg-2-Hll PT N-PT-1 N/A CHM-2084-C ISI-9 Sept. 80 H6-0-R73 PT ~ N-PT-1 N/A CHM-2084-C ISI-9 Sept. 80 RWC-2"Hl PT N-PT-1 N/A CHM-2082-C ISI-9 Sept. 80 R-2$ -Hl PT N-PT-1 N/A CHM-2086-C ISI-9 . Sept. 80 R-2-H3 PT N-PT-1 N/A CHM-2086-C ISI-9 Sept. 80
APPENDIX B - UNIT g3, 40-MONTH CYCLE EXAM CALIBRATION DRAWING REQUEST METHOD PROCEDURES BLOCKS NUMBER FOR RELIEF OUTAGE; REKGKS RPV Circ.
C-4-5 LMT-UT-2 BP-18C CHM-2046-C ISI"2 Fall 79; 1'eld centered on V-4-C C-3-4 LMT-UT-2 BF-18C ,Fall 79; 2'f weld left of N4C RPV Long.
V-4-C LMT-UT-2 BF-18C CHM-2046-C ISI"2 Fall 79; 1'eld below C-4-5 V-5-A LMT-UT-2 BF-18C Pall 79; 1'eld below VES/FLG, right of N3B Closure Head Seam (RCH-3-1C) LMT-UT-2 BF-19C Fall 79; 6" weld from 04 clockvi; Closure Head Meridional (RCH-3-lV) UT LMT-UT-2 BF-'19C Fall 79; 1'eld examined above RCH-3-2C (RCH-3-2V) UT ~ LMT-UT-2 BF-19C Fall 79; 1'eld examined above RCH-3-2C I '
Vessel/Flange UT LMT-UT-2 BF-18C CHM-2046"C Fall 79; 22'eld clockwise from Oo Head/Flange LMT-UT-2 BF-19C Fall 79; 22'eld, Stud gl"30 Main Steam UT LMT-UT-2 BF-18C CHM-2140-C Fall 79; Nozzle/Vessel Nozzle (N3B-26") UT N-UT>>2 BF-18C CHM-2046-C Fall 79; Inner Radius
,'Safe End UT N-UT-1 BF-9C CHM-2140-C Fall 79 I
Core Spray LMT-UT-2 BF-18C CHM-2046-C Fall 79; No'zzle/Vessel Nozzle (N5A-10") N-UT-2 BF-18C CHM-2046-C Fall 79; Inner Radius
',Safe End N-UT-1 BF-6S CHM-2142-C Fall 79 Feedwater LMT<<UT-2 BF-18C CHM-2046-C Fall 79; Nozzle/Vessel M Nozzle (N4B-12") N-UT-2 BF-18C CHM-2046-C Fall 79; Inner Radius R Safe End N-UT-1 BF-15C CHM-2138-C Fall 79 Ch I
(N4C<<12") LMT-UT-2 BF-18C CHM-2046-C Fall 79; Nozzle/Vessel N-UT-2 BF-18C CHM-2046-C Fall 79; Inner Radius
'Safe End N-UT-1 BF-15C CHM-2046-C Fall 79
APPENDIX B - UNIT jj3, 40-MONTH CYCLE EXAM CALIBRATION DRAWING REQUEST EXAM AREA METHOD PROCEDURES BLOCKS NUMBER FOR RELIEF OUTAGE; REMARKS Recirculation Outlet LMT-UT-2 BF-18C CHM-2046-C Fall 79; Nozzle/Vessel Nozzle (N/A-28") N-UT-2 BF"18C CHM-2046-C Fall 79; Inner Radius
.Safe End N-UT-1 BF-8S CHM-2139-C Fall 79 BF-PT-1 N/A CHM-2139-C Fall 79 Recirculation Inlet "
UT LMT-UT-2 BF-18C CHM-2046-C Fall 79; Nozzle/Vessel Nozzle (N2B-12") UT N-UT-2. BF-18C CHM-2046-C Fall 79; Inner Radius jSafe End UT N"UT-1 BF-6S CHM-2139-C Fall 79 PT BF-PT-1 N/A Fall 79 I(N2D-12") LMT-UT-2 BF"18C CHM-2046-C Fall 79; Nozzle/Vessel N-UT-2 BF"18C CHM-2046-C Fall 79; Inner Radius Safe End N-UT-l BF-8S CHM-2139-C Fall 79 BF-PT-1 N/A Fall 79
.,(N2F-12",) UT LMT-UT-2 BF-18C CHM-2046-C Fall 79; Nozzle/Vessel I UT N-UT-2 BF-18C CHM-2046"C Fall 79; Inner Radius
'Safe End UT N-UT-1 BF-6S CHM-2139"C Fall 79 j I PT BF-PT-1 N/A Fall 79 I
I Jet 'Pump UT LMT-UT-2 BF-18C CHM-2046-C Fall 79; Nozzle/Vessel Nozzle (N8A-4") UT N-UT-2 BF-18C CHM-2046"C Fall 79; Inner Radius Safe End UT N-UT-1 BF-2S CHM-2046-C Fall 79 PT BF-PT-1 N/A Fall 79 I
Heah LMT-UT-2 BF-19C Fall 79; Nozzle/Vessel Instr'ozzle (N6-.AI-6")
Noz/Flg., N-UT-1 BF-3C Fall 79; Nozzle/Flange I
Clojure Nuts UT N-UT-5 BF-21 Fall 79; Nuts jjl-30 MT N-MT-1 N/A Fall 79; Nuts jjl-30 VT N-VT-1 N/A Fall 79; Nuts jjl-30 0 COW l Ll HQ O X Closure Studs N-UT-5 BF-20 CHM-2753-C Fall 79; Studs jI1-30 lD Z
N-MT-1 N/A Fall 79; Studs jI22-25 ~ 4J M 00 iQ Closure Washers N-VT-1 N/A Fall 79; Washers gl-30~
CD C
0 APPENDIX B - UNIT j/3, 40-MONTH CYCLE EXAM CALIBRATION DRAWING REQUEST METHOD PROCEDURES BLOCKS NUHBER POR RELIEF OUTAGE; REMARKS Closure Bushings N-VT-1 N/A Pall 79; Bushings f/22-25 Ligaments UT N-UT-8 BF-11C Fall 79; Stud /I1-30 Support Skirt N-UT-2 BF-12C ISI-3 Fall 79; Vessel Clad N-VT-1 N/A Fall 79; 30O 3'-4y" - 210 I 31~I I 17 GR-3-53 (28") UT N"UT-l BF-8S CHM-2139-C Fall 79 KR-3-46 (28") UT N-UT"1 BF-8S CHM-2139-C Fall 79 GR-3-60 (28") UT N-UT-1 BF-8S CHM-2139"C Fall 79 KR-3"37 (22") UT N-UT-1 BF-8S CHM-2139-C Fall 79 GR-3-11 (12") UT N-UT-1 BF-6S CHM-2139-C Fall 79 KR-3-22 "(12") UT N-UT-1 BP-6S CHM-2139-C Fall 79 GR-3"46 (12") UT N-UT-1 BF-6S CHM-2139-C Fall 79 KR-3-42 (12") UT N-UT-1 BF-8S CHM-2139-C Fall 79, Branch Conn.
GMS"3"5 (26") UT N-UT-1 BF-9C CHM-2140-C Fall 79 tiMS-3-15 (26") UT N-UT-1 BF-9C CHH-2140-C Fall 79, Pipe Whip GHS-3-17 (26") UT N-UT-1 BF-9C CHM-2140-C Fall 79 GMS"3-20 (26") UT N-UT-1 BF-9C CHM-2140-C Pall 79 GMS-3-25 (26") UT N-UT<<l BF-9C CHM-2140-C Fall 79 GHS-3"32 '(26'i) UT N-UT-1 BP-9C CHM-2140-C Fall 79, Pipe. Whip KHS-3-3 (6") UT N-UT-1 BF-9C CHM-2140-C Pall 79, Branch Conn.
KMS-3-22 {6") UT N-UT-1 BP-3C CHH-2140-C Fall 79 KMS-3"36 (6") UT N-UT-1 BF-3C CHH-2140-C Fall 79 KMS>>3-59 (6") UT N-UT-1 BF-3C CHM-2140-C Fall 79 KMS"3-70 (6") UT N-UT-1 BF-9C CHM-2140-C Fall 79, Branch Conn.
KMS-3"53 (10") UT N"UT-1 BF-9C CHM-2140-C Fall 79, Branch Conn.
KMS-3-103 (6") UT N"UT-1 BF-3C CHM-2140-C Fall 79 GFW-3-6 (24") UT N-UT-1 BF-9C CHH-2138-C Fall 79 KPW-3-23 (24"-) UT N-UT-l - BF-9C CHM-2138-C Pall 79 KFW"3-28 (20") UT N"UT-l BF-9C CHM-2138-C Pall 79 MV)W GFW-3-14 (12") UT N-UT-1 BF-5C CHM-2138-C Fall 79 Q KFW-3-36 (12") UT N-UT-1 BF-5C CHH-2138-C Fall 79 e ~-.
GFW-3-12 {12") UT N-UT-1 BF-SC CHM-2138-C Fall 79, Pipe Whip ~a GFW-3-26 (12") UT N"UT-1 BF-5C CHM-2138-C Pall 79, Pipe Whip KFW-3-39 (12") UT N-UT-1 BF"5C CHM"2138-C Fall 79, Pipe Whip CO KPW-3-3 (16") UT N-UT-1 BF"7C CHM-2138-C Fall 79, Branch Conn.
APPENDIX B - UNIT g3, 40-MONTH CYCLE EXAM CALIBRATION DRAWING REQUEST EXAM AREA METHOD PROCEDURES BLOCKS NUMBER FOR RELIEF OUTAGE; REMARKS k
I I TSCS-3-425 (12") UT N-UT-1 BF-5C Fall 79 TSCS-3-408 (12") UT N-UT-1 BF-5C Fall 79 TCS-3"417 (10") PT BF-PT-1 N/A Fall 79, Cap Weld DRHR-3-7 (24") UT- N-UT-1 BF-8S CHM-2141-C Fall 79 DRHR"3-6 (24") UT N-UT-1 BF-8S CHM-2141-C Fall 79 DRHR"3-10 (20") UT N-UT"1 BF-8S CHM-2141-C Fall 79 PT BF-PT-1 N/A TRHR-3"191 (20") UT N"UT-1 BF-8S CHM-2141-C Fall 79, Dissimilar DHS-3-1 (6") UT N-UT-1 BF-4S CHM-2141-C Fall 79 DSHS"3-9 (6") UT N-UT-l BF-4S CHM-2141-C Fall 79 t
RCRDS-3" 1 (8") N-UT-1 BF-3C CHM-2143-C Fall 79 RCRDS-3-2 (6") N-UT-1 BF-3C CHM-2143-C Fall 79 DRWC-3-59 .(8") N-UT-1 BF-5C CHM-2145-C Fall 79 DRWC-3-1A (6") N-UT-1 BF-4S CHM-2144-C Fall 79 DSRWC-3"3 (6") N-UT-1 BF-4S CHM-2144-C Fall 79, Pipe Whip TRCIC-3-2 (6") I N-UT-1 BF-3C CHM-2144-C Fall 79 I
THPCI-3-65 (16") UT N-UT-1 BF-7C CHM-2138-C Fall 79 THPCI-3-66 (10") UT N"UT-1 BF-5C CHM-2145-C Fall 79 THPCI-3-70 (10's) UT N"UT-1 BF-5C CHM-2145-C Fall 79, Pipe Whip Pressure N-VT-1 N/A FCV-68"1, FCV-68-33, FCV-1-14, Retaining '.
FCV-1-27) PCV-1-4) PCV-1-18),
Bolting PCV-1-34'CV 1 2u 1 537~
FCV-75-54, HCV-74-49, HCV-74-55, FCV-74-68)74-691) 85-577)
FCV-69"500, 6 FCV-73-2 Integrally'Welded Supports MV5~
KR-3-54 UT N-UT-1 BF-8S CHM"2139-C Fall 79 oo m <<~ v R-3-R1 PT BF-PT-1 N/A ISI<<9 Fall 79 lA W R-3-H3 UT N-UT-1 BF-8S CHM-2139-C Fall 79, Pump.A O ~
MS-3-HAl MT N-MT-1 N/A ISI-9 APPENDIX B - UNIT g3, 40-MONTH CYCLE EXAM CALIBRATION DRAWING RE(}VEST METHOD PROCEDURES BLOCKS NUMBER FOR RELIEF OUTAGE; REMARKS MS-3-HBI MT N-HT- I N/A ISI-9 FW-3-H6 N-MT-1 N/A ISI-9 FW-3-H7 N-MT-1 N/A ISI-9 CS-3-H6 BF-PT-I N/A ISI-9 HS-3-H15 BF-PT-I N/A ISI-9 RWC-3-Hl ,PT BF-PT-1 N/A ISI-9 Support Components R-3-Hl VT N-VT-I N/A R-3-H2 VT N-VT-I N/A R-3-SSI VT N-VT-1 N/A R-3-SS3 VT N-VT-I N/A R"3-H12 VT N-VT-I N/A R-3-H9 VT N-VT-I N/A HS-3-HAI VT N-VT-I N/A MS-3-SSA12 VT N-VT-I N/A MS-3-HA4 VT N-VT-I N/A MS-3-HD3 VT N-VT-I N/A MS-3-GD-I VT N-VT-I N/A MS-3-SSB4 VT N-VT-I N/A
'S-3-SSB5 VT N-VT-I N/A HS"3-HCl VT N-VT-1 N/A MS-3-SSC2 VT N-VT-I N/A MS-3-HC4 VT N-VT-I N/A MS-3-HBI VT N-VT-I N/A FW-3-H6 VT N-VT-I N/A
'FW-3-SSA6 VT N-VT-I N/A FW-3-H5 VT N-VT-I N/A
,FW-3-H3 VT N-VT-1 N/A
,FW-3-Gl VT N-VT-I N/A jFW-3-HIO VT N-VT-I N/A
'FW-3"SSBI VT N-VT-I N/A
- FW-3-SSB3 VT N-VT-I N/A
'FW-3-SSB7 UT N-VT-I N/A FW-3-H7 VT N-VT-I N/A
'CS-3-H5 UT N-VT-I N/A CS-3-HI VT N-VT-I N/A RHR-3-H3 VT N-VT-I '/A H9, H6, 6 H2 APPENDIX B - UNIT 93, 40-MONTH CYCLE EXAM CALIBRATION DRAWING REQUEST EXAM AREA METHOD PROCEDURES BLOCKS NUMBER FOR RELIEF OUTAGE; REMARKS HS-3-H15 N-VT-1 N/A iHS-3-R75- VT N-VT"1 N/A RWC"3-Hl VT N-VT-1 N/A
!HPCI-3-Hl VT N-VT-1 N/A R-3B-H3 VT N-VT-1 "
N/A
,R-3A-H2 N-VT-1 N/A RHR Heat Exch.
'RHRG-10-B UT N-UT-4 BF-26C CHM-2418-B Fall 79,
,',RHRG>>11-B UT N-UT-4 BF-26C CHM-2418-B 79, 3'all Studs N-UT-5 BF-23C CHM-2753"C 79, 12 Studs (Report R-390)
.5'all UT I VT N-VT-1 N/A Fall 79, Ht Exch B-112 Studs Nuts VT N-VT"1 N/A Fall 79, Ht Exch B-224 Nuts IDMS-3-9 (26") UT N-UT-1 BF-9C CHM-2405-C Fall 79 IDSMS-3" 15 (24'I) UT N-UT-1 BF"9C CHM-2405-C Fall 79 IDMS-3-17 (18") UT N-UT-1 BF-7C CHM-2405-C Fall 79
!DMS-3-29 (6") UT N"UT-1 BF-7C CHM-2405"C Fall 79, Branch Conn.
IDSAS-3 (6") UT N-UT-1 BF"3C CHM-2405-C Fall 79 DSAS-15 (6") UT N-UT-1 BF-3C CHM-2405-C Fall 79 TRHR-3-281 (24") UT N-UT-1 BF"26C CHM-2406-C Fall 79 TRHR-3-67 (24") UT N-UT-1 BF-26C CHM-2406-C Fall 79 TRHR-3"39A (24") UT N-UT-1 BF-26C CHM-2406-C
'TRHR-3-197 (20") UT N-UT"1 BF-7C CHM-2406-C TRHR-3-204 (20") UT N-UT-1 BF-7C CHM-2406-C TRHR-3-289 (20") UT N"UT-1 BF-7C CHM-2406-C TRHR-3-183C (20") UT N-UT-1 BF-26C CHM-2406-C CA TRHR-3-374 (20") N-UT-1 BF"7C CHM-2406-C w cn w UT 0 fD Mg TER-3"320 (18") UT N-UT-1 BF-7C CHM-2406-C OI C-W TRHR-3-104 (18") UT N-UT-1 BF-7C CHM-2406-C ~o TRHR-3-253 (16") UT N-UT-1 BF-7C CHM-2406-C M ~
TRHR-3-494 (10") UT N-UT-1 BF-5C CHM-2406-C CO TRHR-3-448 (6") UT N-UT-1 BF"3C CHM-2406-C f
RHR Piping Bolts VT N-VT-1 N/A Studs $/1-24 (Flange Off Pump A)
UT N-UT-5 BF-22C Studs /fl, 23 6 24 (Pump A Flange RHR'Piping Nuts VT N-VT-1 N/A
APPENDIX B - UNIT 83, 40-MONTH CYCLE EXAM CALIBRATION DRAPING REQUEST EXAM AREA METHOD PROCEDURES BLOCKS NUMBER FOR RELIEF OUTAGE; REMARKS H-65 VT N-VT-1 N/A H-121 VT N-VT-1 N/A H-67 VT N-VT-1 N/A H-62 VT N"VT-1 N/A R-64 VT N-VT-1 N/A H-124 VT N"VT-l N/A H-125 VT N-VT-1 N/A H-4 VT N-VT-1 N/A H-14 VT N"VT-1 N/A H-16 VT N-VT-1 N/A H-10 VT N-VT-1 N/A H-8 VT N-VT-1 N/A H-26 VT N-VT-1 N/A H-19 VT N-VT-1 N/A H-21 VT N-VT-1 N/A H-23 VT N-VT-1 N/A H-29 VT N-VT-1 N/A H-146 VT N-VT-1 N/A R-70 VT N-VT-1 N/A H-160 VT '-VT-1 N/A H-'145B VT N-VT-1 N/A H-6 VT N-VT-1 N/A RG-1-ST VT N-VT-1 N/A RG-1-2ST VT N-VT-1 N/A 't$ M tP N-VT-1 HQ H-54 VT N/A OQ 2I N-VT-1 e c R-35C VT N/A 4J
'H-158 VT N-VT-1 N/A t4 ~
'R-54 VT N-VT-1 N/A
~ A Valves
,74-57 N-UT-5 BF-22C N/A Studs $/1, 27 6 28 (1(" Dia.)
74-559A N-UT-5 BF-22C N/A Studs g6, 7, 8 8 (l<" Dia.)
- 74-57 N"VT-1 N/A 20 Nuts S Studs
'74-559A N-VT-1 N/A 28 Studs 8 56 Nuts74-150 N-UT"5 BF-23C N/A Studs 914-18 74-150 N-VT-1 N/A Studs APPENDIX B - UNIT g3, 40-MONTH CYCLE EXAM CALIBRATION DRAWING RE(}VEST METHOD PROCEDURES BLOCKS NUMBER FOR RELIEF OUTAGE; REMARKS RHR Pump Bolts VT N-VT-1 N/A Studs gl-24 (Pump A)
UT N-UT-5 BF-22C Studs gl, 2, 6 3 (Pump A)
RHR Pump Nuts VT N-VT-1 N/A Nuts gl-24 (Pump A)
Integrally Welded Supports RG-1-ST MT N-MT-1 N/A RG-1-2ST MT N-MT-1 N/A H-158 MT N-MT-1 N/A R-50 MT N-MT-1 N/A H-122 MT N"MT-1 N/A H-62 MT N-MT-1 N/A H-6 MT N-MT-1 N/A Support Components MSH-3-12 VT N-VT-1 N/A MSH-3-7 VT N-VT-1 N/A MSH-3-10 VT N-VT-1 N/A MSH-3-13 VT N-VT-1 N/A MSGEH-1 VT N-VT-1 N/A MSH-3-17 VT N-VT-1 N/A HPASH-1 VT '-VT-1 N/A
'PASH-3 VT N-VT-1 N/A HPASH-8 VT N-VT-1 N/A HPASH-10 VT N-"VT-1 N/A
. HPASH-4 VT '-VT-1 N/A HPASH-18 VT N-VT-1 N/A H-158 VT N-VT-.1 N/A R-36 VT N-VT-1 N/A
'H-82 VT N-VT-1 N/A
- .H-84 VT N-VT>>l N/A
- H-85 VT N-VT-1 N/A
,H-73 VT N-VT-1 N/A
'R-35 VT N-VT-1 N/A cn
'H-98 N-VT-1 W Ch CU VT N/A H tj
=R-50 VT N-VT-1 N/A ,0 C R-63 VT N"VT"1 N/A N-VT-1 t4 ~
H-55 VT N/A A H-122 VT N-VT-'1 N/A Q3 H-56 VT N-VT-1 N/A OO
BFNP SI 4.6.G Page 325 SEf'29 1981 APPENDIX C
UT CALIBRATION INFODfATION BROWNS FERRY NUCLEAR PLANT REACTOR COOLANT SYSTEM Actual Nominal Nominal Pipe
~Sseem Size Size Function Material Test Block Wall Sch Main Steam 26. 0" 2 6ll Main Steam lines A155 KC70 BF-9-C 1.012 6.625" 6" Main Steam relief A106 Gr. B BF-3-C 0.719 Sch 160 lines l
Feedwater 24 0" 24u Feedwater into A106 Gr. B BF-9-C 1.531 Sch 100 dry well 20.0 2 Oil Feedwater in A106 Gr. B BF-9-C 1.281 Sch 100 dry well 12.75" Feedwater to vessel A106 Gr. B BF-5-C 0.844 Sch 100 Recirculation 28. 0" 2 8 II Recirc. outlet lines A358 304SS BF-8-S 1.272 22.0 2 2l I Recirc. inlet header A358 304SS BF-8-S 1.030 12.75" ] 2II Recirc. inlet to A358 304SS BF-6-S 0.789 vessel I I t 5 II 4 II 'ecirc. bypass line A376 304SS BF-2-S 0.337 Sch 80 I
Core Spray 12.75" 12" Main core spray (unit 1) A358 304SS 0.688 Sch 80 line BF-6-S'F-5-C (unit 2 & 3) A336 Gr. 6 10.75" Core spray to (unit 1) A358 304SS BF-6-S .0.594 Sch 80 vessel (unit 2 & 3) A336 Gr. 6 BF-5-C
,RHR 24 01I 24 II RHR to recirc. A358 304SS BF-8-S 1.219 Sch 80 inlet
- 20. 0 20I I RHR to recirc. A358 304SS BF-8-S 1.031 Sch 80 outlet CO 20.0 20II RHR to recirc. A106 Gr. 6 BF-9-C 1.031 Sch 80 MM outlet e c 6.625" 6" Head spray line A358 304SS BF-4-S 0.432 Sch 80 ~ h) ~
Head spray line A106 Gr. B BF-3-C 0.432 Sch 80 ~
CX)
Ch
Continued Actual Nominal Nominal Pipe
~Sstem Size Size Function Material Test Block Wall Sch HPCI 16. 0" ) 6l I Line of f of feed- A)06 Gr. B BF-7-C 0.844 Sch 80 water 14.0 )4ll Line off of feed- A)06 Gr. B BF-7-C 0.750 Sch 80 water 10.75 10" Line off of main A)06 Gr. B BF-5-C 0.504 Sch 80 steam Reactor 6251t 6ll Line off of 20" 304SS BR-4-S 0.432 Sch 80 cleanup RHR 4.5 4tl Line off of feed- A106 Gr. B BF-I-C 0.337 "
Sch 80 water 8 625" 8" Line off of feed- A106 Gr.,B BF-5-C 0.593 Sch 100 water RCIC 625tt 6ll Line off of 8" A)06 Gr. B BF-3-C 0.432 Sch 80 cleanup CRD Hydraulic 4.5" 4tl Line to RWCU BF-27-C 0.337 Sch 80 return Long weld neck for vent nozzle BF-3-C 13/16" Long weld neck for 6" instrument nozzle BF-3-C 12/16" Closure head flange to head weld BF-19-C I
l Shell flange to shell weld BF-10-C I
Head welds BF-19-C Nozzle to shell welds BF-18-C M alta Nozzle to head welds BF-19-C O
'V CC)
OO
5.00R Q 25~0 RMS FlNISH ENO RADII OR
- 3. 0 RUNOUT PERMISSIBLE 2lo M IMCL.
i Ls REF. I.0 REF. .50 L
III
- 075 Iil I I 075 I I li I C
.075 NS aFS~ M 2.00 55 9 I.50 A
,375 TI,"I'hCS:.'.ll: Vwl.l. I. 7 AU1HORIl UI9ISl1 1ti Qr ra.YJLg PB>>l>jl{ )r1lii P 2.00 SAFE-ENO TEST BLOCK, BF-l5-C MATERIAL- C.STL.-A-5I9 Figure 5 I/8 OIA, HOLE
REFERENCE:
APPENDIX IK OF 8 8 PV CODE SECT.QIZ'SME 5~.LLE: N T$ SufsMlTTEO AVPAOVEO o 1< I:8-'74 NUCLEAR SF'RVIGES CORP, ie:fr E I 4 I i1(fY 1'8 Acro Cl!ECKEO ] /g]fO 1000012
BFNP SZ 4.6.G Page 329 CALIBRATlON BLOCK SEi 29 1981 BF- l2- C i
2l/4" II 2
l2 3/4 Extraneous hole Basic calibration sides parallel holes O.I875 within -.003 I 3/8 DIA A DIA. 3I I 3/4ll l25 CALlBR ATlON BLOCK BF-I l- C 2
II 0.250 DIA ~i, ii 4II ll l'/2" +ll/8" 24 l 25 r
1.625 2 II
+
sides parallel 0.3l25 Ola.~
~ 6.5" within +,003 O.l875 Dia.~
l.625 llaJIC itAyj ~ r l
CALlBRATlON BLOCKS Figure 2
,'TS ... (. ~
~
'1
' -'. l l.- 20-72, l ~
3 N1 ~ w' r ~ ~
jf// u 'Ctte-2080-a'
BFNP SI 4.6.G Fage 330 SEP2) )g8t
- 0. 75 O. I 25 DIA. l25 WIthIn +.005 I/2 I25 l6 II/2" CALIBRATtON BLOCK BF-8-S et BF-9-C O2 I/2 48 0.3I 25 D I A.
II
~8 CALlBRATION BLOCK BF- lO-C CALlBRATlON BLOCKS
~
figure N ...
=..i'..t. QTS ' l-20-72.
I h:..g,~ht h 0 2 3 I
I CHM-2080-A
~, ~ gyJP
BFNP SI 4. 6. {>>
8 II Page 331
)
, SEPag>98>
/>>
//I/
/'9 /2 T 3/32 DIA 3/32" DIA III O,D.
+45 GAL. BLK.
OIA>> L 4ll ll NO. . 337 ~ OI7 l80o 9 BF-I - C 6>>I 3/4 ~ 038 I 20o I2 QF-2-S 8>>l BF-3-C 3/4 038 I20o l2 BF-4-S BF-5-C lo 3/4 ~ 038 l20 I2 SF-8-S I4 3/4 . 038 90o l2 BF-7-C 45 I.D. 8 = I Mrn{eum A-A CALIBRATION BLOCK F{gure 4 NTS .~ tl-,20-72 .
" .'3 '3
'lfo 'r Hk -'Oeo-A
~"
Ii 69 45+
LIAXr L
49r z.'gi'1 m'S l
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W Ch&
OI Hg U e c
+ Lrl Ch CD t4 i)
CO
>I>'.r 'c I hier 4c~ r.~s .Cr C CC ~ err \ r oared lLTRASONIC CAIS RATIONS 6LODC fOR FEEOAATER ROZZLE SRQWICS FERRY LEXLEAR FLANT
2I.06'3I'4.69 IOe00'k9'J25 g Sr UR MAX I200'25 RIM y Y
~CLA0DINC E 309 STAINLESS STEEL I
00'0.26
%CA
.I9'3.95 US 6"1 09 I9 C lA W lgiNAS'4r VALLST AVIAOri1Y ht l4 Ct KT;0 wrCAlga ULTRASONIC CALIBRATICNQLOCK FOF.CLAO FEEOlNATER NOZZLE SROViNS FERRY NUCLEAR PLANT
~ "~ ~ ~ ~0 I hs
/g" DIA. HOLES - DR ILL E D
~REAM 'S DEEP.
1 Y P. Co PL AC E G V
I IO I
O>>
II.
I. 50 SIDE VIEW B.QO
~
2.00 LONG X l4 DIA.
FLATBED MILL NOTCHES.
2R. OO SO A
Z.OQ G.OO foal W ca
- 0) H as
'SCALE W = I" ~ e s IA M TOP VIEtnl 4 v)
NOTL= I, (0 MATER IACQA ~~ 9 3 SECTION A-A
,. I 2S'I APP I'RAS NIC CALIBRATIOI I BLOC K BFNP BF-l B-C ORCUS 7l//0 c.
1+ DIA. H OL E S - DR I L L E D
'E OKER.
ITREAM YP. 8 PL AC. E S IJ Ei.OO" 300 II'L 2.00', ID
. I.OO SIDE ViEW P.OO 2.00
.'2.00 LOIAICIX /4 DIA.
20 . FLATEIAID MILL IAIOTCHK5.
2A. OO' A
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C.~
~
O TOP ViEw NOTE: ~I MATERIAPA E'3 E IAI ~
a ULTR+5 ~IC CALIURATION RECTION A-A ELOCK BFNP BF icI-C lfllO rII EI a>Sa.C
~
MATERIAL UMBER BLOCK hlUMBER I EO X
X Al9'5GP.B I I
LI IO'I93GRB AI93 GR \4 III AI93GRST 23 IO AI93 GP,67 2,%
I I AI93 C 9. 87 8,5 Ql
>I" QIA. FBH b
CC)
Ill CG I II S.OO llI TYP. hlOTE:
I. PLUS ~i'b OIA. FBH WITH I:I SIMILIAR MA TE Rl AL .
E REPLACE X X 1M BLOCK NUMBER WI'TH NUM BER FROM 'TABLE. VLTRASOhllC CALIQRATIOM BLOCKS BENI STUQS AklD hluTS
IRr gv lg Ill I
I Pl 0) tA 0/i bS MW NOTE NUMBE R Sj ~ f5 HO L E III LO vC)
Q3
.0375 ' CO SCALE- I r I'OTE:-
MATERIAL ALOD CrR. B.
SECTION AA ULTRASONIC CALIBRATION BLOCK BF IMP BF- 2'-C
BFiVP SI 4.6.G Page 338 SEI'29 198 f
.OB'7>>
SECTION AA h4O'TEI NOTE BLOCK NUMBER BLOCK I'O BE MADE FROM
+" OIA. BCH I &0 PIPE A10$ GRB
~rsz 0 ULTRASONIC CALIBRATION BLOCK
,-J &FNP j BF-rr7 C.
BLOCK KL 3
FLAT BOT'I vhI CA U Q QII M
III WW 1 (u a I I I
I I I
I CO I (
I I Z I
'I I IR OCR 0 NATCRIAL I
I ~
CX 7$ A ISI-OI Cy I
I I
I ~
A NOT E: I. IIIII SIIALLB SAOIE hIATER. 'L PI.I SHALI. BE A PRESS
~ I AS PO'LEB STOCK FIT INTO THE P QRILLEO 2 SUBSTITUTE BF FOR BROWSES FERRY 8
FI.AT BQT TOM IIOLE NUCLEAR PLANT IN PLACE OF THE XX IN THE BLOCK NUMBER 1CNtvC55CC VAL'1 AUIIoOIIaOO OITO4a OO OOOO OoOOVOlgo STUO ANO BOLT CALIBR*TIOI BLOCK Ll ~
--.-4-r O~g ~
- - CN>> 'I'I
~ ~
C
BFNP SI 4.6.G Page 340 SEF'ZS >881 APPENDIX D
BFNP SI 4.6.G APPENDIX D Page 341 Data Sheet 1 SEI'29 198i.
NOTIFICATION OF INDICATION PART I- FINDINGS Examination Report No. Plant/Unit Weld Map Number Examination Performed Description of Indication: (Attach Sketch/Photograph)
Signature of Examiner/Certif. Level Date Signature of Field Supervisor (Contractor)
Date Baseline and ISI Representative Date PART II - DISPOSITION Disposition Approved by TVA Level III Examiner Date Verification of Completed Corrective Action by Baseline and ISI Representative Signature Date
BFNP SI 4.6.C:
Page 342 SEP 29 l981 APPENDIX E
AUGMENTED INSPECTIONS UNIT 1 CORE SPRAY EXAMINATION.AREA EXAM CALIBRATION DRYING REQUEST IDENTIFICATION METHOD PROCEDURES BLOCK NUMBER FOR RELIEF DSCS-1-6, 5, 4, 3, 2, 1, NUT-NC-lA BF-6S fall 1977 DCS-1-8; 7, 6, 5, 4, 17, 16, 15, 14, 13, NUT-NC-1A BF-6S fall 1977 DSCS 1 1>> 2 3 4>> 5 6>>
7,, 8, 9, 10, I
ll, 12, 13 UT BF-UT-8 BF-6S December 1978 DCS-1-4, 5, 6, 7, 8, 13, 14, 15, 16, 17, 18, 9 UT BF-UT-8 BF-6S December 1978 I
DSCS-1-13>> 6, 5, 4, 3, N-UT-1 BF-6S January 1980 D/S-l-18, 17, 16, 9, 7, 6, 5, "14, 15 N-UT-1 BF-6S January 1980 arnica CA Pl I Hg 0)
C MA CO
EXAMINATION AREA EXAM CALIBRATION DRAWING REQUEST IDENTIFICATION METHOD PROCEDURES BLOCK NUMBER FOR RELIEF Feedwater Nozzles (12")
- b. inner radius NUT-NC-1C BF-llc fall 1977
- c. Nozzle-to-safe end Feedvater Nozzles (12")
- a. Bore December 1978
- b. Inner radius
- c. Nozzle-to-safe end Feedwater"Nozzles (12")
- a. 'Bore b; iInner radius
- c. Nozzle-to-safe end N-UT-l BF-15C January 1980
AUGMENTED INSPECTIONS UNIT 1 RWCU EXAMINATION AREA EXAM CALIBRATION DRAWING REQUEST IDENTIFICATION METHOD PROCEDURES BLOCK NUMBER FOR RELIEF DRWC-1-1 N-UT-1 BF-4S January 1980 DRWC-1>>2 N-UT-1 BF-4S January 1980 DRWC-1-3 UT N-UT-1 BF-4S January 1980 DRWC-1-4 N-UT-1 BF-4S January 1980 DSRWC-1-1 N-UT-1 BF-4S January 1980 DSRWC-1-1A UT N-UT-1 BF-4S January 1980 DSRWC-1-2 N-UT-1 BF-4S January 1980 DSRWC-1-3 N-UT-1 BF-4S January 1980 D/RWC-1-4 UT N-UT-1 BF-4S January 1980 DSRPC-1-5 UT N-UT-1 BF-4S January 1980 I
I DSRWC-1-6 UT N-UT-1 BF-4S January 1980 I I DSRWC-1-7 UT N-UT-1 BF-4S January 1980 l
Augmented Inspections Unit 2 Core Spray EXAM- CALIBRATION DRAWING EXA.fINATION AREA METHOD PROCEDURES BLOCK NUMBER REMARKS TSCS-2-409,420,418,424, UT BF-UT-8 BF-5C CHM-2071-C Spring 7&
425 TCS-2-401,402,403,404, BF-UT-& BF-5C CHM-2071-C Spring 78 405,406,407,408,410, 422,421,417,419,423, 426
AUGMENTED INSPECTIONS - UNIT 2 - FEEDVATER NOZZLES EXAMINATION AREA EXAM CALIBRATION DRYING REQUEST IDENTIFICATION METHOD -
PROCEDURES BLOCK NUMBER FOR RELIEF Feedwater Nozzles (12")
and 57 scans
- b. Inner radius BF-UT-5 BF-llC spring 1978; 70 scan
- c. Nozzle-to-safe end BF-UT-8 BF-15C spring 1978; reports R-70 + R-75 Feedwater Nozzles (12")
- c. 'ozzle-to-safe end N-UT-l BF-15C fall 1980; reports R-125 + R-130 CQ acne C
(Q ma CO
AUGMENTED INSPECTIONS UNIT 2 RWCU EXAMINATION AREA CALIBRATION DRAWING REQUEST IDENTIFICATION PROCEDURES BLOCK NUMBER FOR RELIEF DSRWC-2-1 BF-4S CHM-2073-C fall 1980 DRWC-2-2 BF-4S CHM-2073-C fall 1980 DRWC-2-3 I
BF-4S CHM-2073-C fall 1980 DSRWC-2-1A I
BE-.4S CHM-2073-C fall 1980 DSRWC-2-2 UT N-UT-1 BF='4S CHM-2073-C fall 1980 I
DSRWC-2-.4 N-UT-1 BF-4S CHM"2073-C fall 1980 DSRWC-2-3 N-UT-l BF-4S CHM-2073-C fall 1980 I
D/RWC-2-5 I
N-UT-1 BF-4S CHM-2073-C fall 1980 I
DSRWC-2-6 "
I BF-4S CHM-2073-C fall 1980 I
DSRWC-2-7 N-UT-1 BF-4S CHM-2073-C fall 1980
) i DRWE-2-4 N-UT-1 BF-4S CHM-2073-C fall 1980 l
DRWt:-2-1A N-UT-1 BF-4S CHM-2073-C fall 1980 DQWC-2-1 N-UT-1 BF-4S CHM-2073-C fall 1980 l
I I
l I
C Q C) H 00 i
0 O'0 1
l Q) Q Q3 I
CO
Augmented Inspections Unit 3 Core Spray EXL~f CALIBRATION DRAWING EXAMINATION AREA METHOD PROCEDURES BLOCK NE ABER REMARKS DSCS-3-1,2,3,4,5,6,7, UT BF-UT-8 BF-6S CHM-2142-C Fall 78 8,9,10,11,12,13 DCS-3-4-5,6,7,8,9,13, UT - BF-UT-8 BF-6S CHM-2142-C Fall 78 14,15,16,17,18 TSCS-3-4-2,418,423,409, UT N-UT-1 BF-6S CHM-2142-C Fall 79 408,425,404,420,418,402 TCS-3-417,401,403,405, UT N-UT-1 BF-6S CHM-214 2-C Fall 79 406,407,410,419,421,
-422,424,425,426 DSCS-3-8, 3, 1, 2, 9, 10,4, UT N-UT-1 BF-6S CHM-2142-C Fall 79 2,13,11,12,5,6 DCS-3-5-15,4,14,13,7,18, UT N-UT-1 BF-6S CHM-2142-C Fall 79 I
~
8,7,16,6,9,17
AUGMENTED INSPECTIONS UNIT 3 FEEDVATER NOZZLES EXAMINATION AREA EXAM CALIBRATION DRAWING REQUEST IDENTIFICATION METHOD PROCEDURES BLOCK NUMBER FOR RELIEF Feedwater Nozzles (12")
- b. Inner radius UT BF-UT-5 'BF-11C fall 1978; 70 scan
- c. Nozzle-to-safe end Feedwater Nozzles (12")
a'.- Bore UT BF-UT-2 BF-16C CHM-2138-C fall 0
1979; 36 , 45 , and 57 scans f
b'. Inner radius UT N-UT-2 BF-18C CHM-2138-C fall 1979; 70 scan
- c. Nozzle-to-safe end UT N-UT-1 BF-15C CHM-2138-C fall 1979; N4B and N4C only I
I I
j
BFNP SI 4.6.G Page 351 SEP 29 1981 APPENDIX F
BFÃP SI C.6.a Page 352 SEP 88 1981 APPENDIX F Data Sheet 1 BROWNS FERRY NUCLEAR PLANT UNIT, CYCLE INSERVICE INSPECTION FINAL REPORT Reviewed hy:
NCO QA Staff, Chief Plant Superintendent
BFNP SI 4.6.G Page 353 SEP 29 1981 APPENDIX G
BFNP SI 4.6.G Page 354 REOUEST FOR RELIEF ISI<<2 SEP 89 198'I
~Con anent": Reactor Pressure Vessel Class:
Function'. Prcssure-retaining component.
n Test Requirement: Vclumetric cxcwn. +ion of reactor pressure vessel pressure-retains.ng velds, examination categories B-A and B-B; Basis for Relief: The Brovns Ferry Nuclear Plant vas designed and under construction before the issuance of Section XI.
As a result, only those velds above the sacrificial shield arc accessible for inscrvice inspection. Access has not been provided in the sacrificial shic1d area for external examinations nor does the BUR design permit internal examinations in this area. Only those velds above the sacrificial shield and portions of velds a may bc accessible at nozzle access points vill be examined durinz the inn~rvice inspection intervals.
Alternate Inspection: Hone.
BFNP SI 4.6.0 Page 355 RE UFST FOR RELIEF ISI- SEP 2> 198]
Comnonents: Reactor Pressure Vessel Support Skirt Class:
Function: Support component.
Test Renujrement: Volumetric examination of support attachment veld to vessel, examination category B-H.
Basfs for Relief: Approximately 6 feet of. the attachment veld vould require examination to meet code requirements.
Hovever, nonremovable reactor vessel insulation limits inservice examination. .~ access ports, approximately 180 degrees apart, provide. access for examination of tvo 2-foot lengths. Four feet of the support skirt-to-reactor vessel veld vill be ultrasonically examined during each inspection interval.
Alternate Insnec ion Hone..
BFNP SI 4.6.G Page 356 SEP 29 l98t REQUEST FOR RELIEF ISI-4
~Com onents: Reactor Recirculation Pumps stems:
Function: Provides a variab'le reactor power rate by varying core coolant flow rate.
Test Re uirement: Visual examination of pump internal pressure boundary surfaces, examination category B-L-2.
Basis for Relief: In absence of required maintenance, 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.
Oisassembly of this pump could requi re transport oF the motor outside of containmei t; 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 wnrk. Radiation dose rates of the pump exterior will average 100-300 mrem/hour, and pump internal dose rates will average 10"20 reit'/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 employee exposure, potential damage to safety-related equipment, and cost in dollars.
In addition, the multiple units at Browns Ferry Nuclear P'lant operate under simi)ar conditions. Threfore, we feel that if a pump from one of the multiple units is disassembled for maintenance during a 10-year interval, the visua) examination performed wil I be representative of the pump cordi t ion For each uni t. This would avoid unnecessary exposure of employees to high radiation aose rates noted. Me conclude that if one pump is disassembled For maintenance during the 10-year intervalt the visual examination performed satisfies exar,.inati"n category B-L-2 requirements for the three multiple units.
Oisassemb!y of the pump solely for visual examination is impractical.
Alternate Inspection: The internal surfaces of the recirculation pump casing will be visually examined whenever the surfaces are made accessible when a pump From any unit is disassembled for maintenance purposes. If during the 10-year interval a pump from any .unit is not disassembled, a punp from one unit shall be examined from the exterior. This shall be accomplished by taking ultrasonic thickness measurements of the pump casing.
BFNP SX 4.6.G Page 357 RE VEST FOR RFLIEF ISI SEP 29 198>
~Con anent": Valves Exceeding 4-inch Nominal Pipe Size Class:
Function: Various functions.
Test Rc uircmcnt: Visual examination of valve internal pressure boundary surfaces, exnmination 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. Host Class 1 valves, particu1arly containment isolation valves, are disassembled frequently for maintenance. In addition, the multiple units at Brovns Ferry operate under similar conditions. If a valve from one of the multiple units is disassembled for'aintenance vithin a 10-year interval, ve feel that the visual examination performed vould be representative of all three units and vould be sufficient to sa isfy the examination requirements for all three units for that particular I
valve classification as defined in examination category B-M-2.
Vc conclude that if. one valve in each group of valves of the same constructional dc"ign and manufacturer
'I that perform similar functions is disasscmblcd from any unit during the 10-year interval, the visual examination performed satisfies examination category B>>M-2 requirements for the three multiple units.
BPNP SI 4.6.G Page 358 SEJ'29 198) c Alternate Inancction: If a valve from a particular classification has not been disassembled as the end of the inspection interval cpproaches, a cas -by-case study vill bc made to detcrminc the practicality of disassembling a valve from one of the multiple units solely for visual examination (determine if draining the vessel vould be required, ctc.). 'If necessary, a request for rc1ief v111 be issued at that time.
0 BFNP SI 4 ~ 6.G Page 359 R UFST FOR RH,IEF ISI-6 SEI'29 1981 Comuoncntsl Control Rod Drive Housing Mclds Class:
Function: Pressure-retaining component.
Test Rc uircmcnt: Volumetric examination of peripheral CRD housing velds, examination category B-O.
Basis for R lief: Should the CRD housing veld fail, the leakage path to.
the failure meets the make-up exclusion criteria and is therefore excluded from volumetric examination in accordance ltith DlB-1220(b)(1). The make-up supply
~
system is eouivalcnt to 4-inch nominal pipe size'he smallest leakage path area,~ould be realized betveen the guide cap and therma1 sleeve as shovn on the attached aiagrams. The folloving calculations verify exclusion of volumetric examination in accordance with ZVB-1220(b) (1):
'I For 3>>inch nominal pipe size (maximum code exclusion):
D = 3.068 inches
'I A ~ {ft ) {D /4),.+here A ~ internal transverse area D ~ inside diameter A3-i 7.39 in. 2 For the thenml slcevel DTS ~ 4.25 inches ATS ~ 14.19 in. 2
BPNP SI 4. 6.0 Page 360
~ 2\
. SEP29 1981 R UEQT R)R RELTFF ISI>>6 Basis for Relief: For the guide cap:
Continued)
DGC
= 4.125 inches AGC 13.36 in. 2 Total leakage path area:
LP 'S A GC
~ 14.19 in 2 13~36 in 0 83 in~
2 A3 in ~ 7.39 in. 2 A ~ 0.83 in.
Ther~fore, ALp ~ A3 i.
Alternate Insnection: All peripheral CRD housing ~elds shall be visually excuaincd during the systen hyd"ostatic pressure tests in accordance vith IVB-1220(c). h
BFNP SX 4.6.C Page 361
~E~29 198f EO'itliCL RCO VFLGCtfr LIUIIER cotiraoL Roo ORIVE TO
~> GUIOE TUSE COUPLItiC MCUStNG TO vr SSEL "PELO R ACIGR VESSEL sorrQA /j gtl A jj HOKE: A CIRCLEO NUVSER THERMAL Sl EEVE INOICATES A PRESSURE POIN T.
ORIVf, NCUSI:IG
$ rop pISTQ'I ANO SEALS IIIOEX TUSE p CUIOE CAP Cp~',~l.~,'9'jjj'I COTTER PLV f<)'~~ COLLfT.FUIGE RS g 4 ~ CCLLET SPRIIIG w) I,~+V~
P CQLLET PISTC'.I ANO RUiGS SPRING ~ I~
~
IIASHERS SUFFER !I':g<<3 PISTON HOLE I 't,gi r ORIV.
TUOE Pl'IION AHO <EALS PRESSURE HOUSIIIG TO f LANCE 'WELO OVER PORT f LAIICE IiUS DRIVE WITIIORAW PRESSURE a
LINE ~~
+tt ~p UNDER PORT ORaVE INSERT
~
HOUSING
'LAIIC'E "Q LIIIE pf'ALLCHECK VALVE
/~>> VEIIEL PCRIS cwivE I/AIN fLAtiCE wELOLO PLUG I/AIR fLAVCE BOLTS PISTON: 'b'.,i; POSITICII tticICAICR wELL PISTON TUSE To
-'ii.
~
TUSf. HEAD wELO PISIO;I IUSE.HEAD L I t".r RltiG rLANcf RINC FLANCE SOI.T L~g
'S~
PQS(flQH ItiOICATOR %ELL P0$ ITIOtt ItiolCATCR To PISTON TOBE HEAO WELO HOUSItiC BROWHS FERRY HijCLEAR PLANT FlHAL SAFETY AHALYSIS REPORT Control Rod Drivo, Schomatic Oiagram FIGURE 3A 6
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B i'iVI'I 4.6eG Page 363 SEP P.9 1981 RE UEST FOR RELIEF ISI-7
~Com onente: Inaccessible Residual Heat Removal, Main Steam, and Feedwater Circumferential Pipe Welds Class:
Function: Pressure-retaining component Test Re uirement: Volumetric examination of pressure-retaining welds in piping, examination category B-J Basis for Relief: Five RHR welds are located inside containment penetrations and are inaccessible for any type of examina-tion. Four main steam welds and two feedwater welds are located under rigid pipe restraints and are inaccessible for volumetric examination. These welds are identified in the inservice inspection program.
Alternate Ins ection: A "best effort" visual examination will be performed during system leakage and hydrostatic pressure tests.
8 re P SI 4.6.G Page 364 SEP 29 >>8>
REQUEST FOR RELIEF ISI"8 Com onents: Pressure-Retaining Welds in Piping Class: I and 2 Function: Pressure-retaining component Test Re uirement: Volumetric examination of longitudinal, circumferential, and pipe branch connection welds, examination categories 8-J and C-F.
8asis for Relief: ln some cases it wi I 1 be i'mpractical 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 wi 11 be noted on the ultrasonic examination data sheets.
Alternate Ins ection: 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 we)d(s) .
L ~
BFNP Sx 4.6.a Page 365 SEP 29 198j I ~I "0 {C rn t >>)u~.:fl)
Cia.,s l Wfcld: f4.< uirinn Al ternate Surl ace Examination Wclfl Identification Limitation GFW-3"7 Valve Welded to Tee GFW-3-2l> Val vc Welded to Tee Class 2 Welders uirin Alternate Surface Rraninatinn Class 2 systems were not originally sub)ect to baseline examination requirements. Welds which are determined to ref.>>4~o alternate surface examination during the conduct of inservice examinations will be included in this tabulation.
BFNP SZ 4.6.G Page 366 SEP 29 1981 REOIK T FOR R."LLIEF ISI-O
~Oner oner.t": Xntcgrally-Melded External Support Attachments for Piping and Valves Class:
Function: Support components.
Test Rc uircment: Volumetric examine ion of the support attachment vclds, examination category B-K-1.
Basis for Relief: During thc first Brovns Ferry baseline inspection, thc ultrasonic examinations of the integrally<<welded Class 1 supports vere meaningless because of the lack of penetration indications that existed for the fu11 length of the support velds. The supports, vere fabricated to ANSX B31.1.0 and General Electric Co"pany specification 21A2100. The GE specification required a full penetration veld and surface examination requirements, vhich would not verify penetration. The TVA Division of Engineering Design has taken actual veld dimensions of randomly-chosen piping supports and compared the load capabilities I
of these velds as installed to the loads based on; design the sulfports vould sec during operction. As indicated in the attached analysis, all suppor s studied have high factor of safety in their load-car.;ing capability; therefo c, vc feel the integrally-welded supports on the primary coolant piping are acccp able as installed. Future ultrasonic examinations of these supports would be meaningless.
BFNP SI 4.6.G Page 367 SEP 29 1981 RE Vj.'ST FOR RET.IZF ISI-Altcrnatc Incncction: Class l integrally-welded supports Mill be liquid penetrant exaained in place oi ultrasonic examinations.
The liquid penetrant cxaninations perforaed during each inspection interval vill cover 25 percent of'he integrally-welded supports.
BFNP SI 4.6.3
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BFHI'X 4.6.G Page 370 ENCLOSURE SEP 29 )98~
ADDITIONAL INFQRKKTXOII REGARDING X'ASHR'/XCH XNSPI;CTXON PROGI'AII REQUEST FOR RHLXHF XSX-9 BROGANS FERRY NUCLEAR PI.SPIT UNXT 3 (DOCKET NO. 50-296)
To provi<le justification for Request for Relief XSX-9 an analysis was performed on a selection of integral supports that arc subject to fati"ue loading. Integral welds in the latest sampling indicated substantially higner 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. Ba ed on these results, we believe that the in't:egral support welds are entirely acreptab3e, and relief from the inservice volumetrtc e..amination requirements of the AS'.IE Section XX Code is justizied.
l$ l<NP Sr 4.6.C Page 371 ATTACIMENT 8EF'9 '1981 ASSUMPTIONS
- 1. Duc to lack of full penetration, fillet welds were assumed with a base dimension equal to the specified penetration groove opening.
- 2. Restraint loads as specified by t:hc support assembly drawin< s vere applied.
Codex'.
Eff ctivc arcs fillet velds in accordance with paragraph 3.
XVXX 2452 ', oF, thc Appendix XVXI,Section IXX, was ASME Shca" and tensile stresses in thc welds. vere combined by the ma..imu".,) shear stress formula to. compare with the fillet weld shear allo<.ablcs presented in paragraph NE-3291.1-1, subsection M', sect.'.on IXI, ASIDE Code. The minimum specified shear allow-'blc is applied in all cases.
- 5. No stress conccntrat,ion factors vere applied. The high fact:ors oF.. aCety more than offs<=t any conccnt;ration effects.
SU!DIARY Ol" RPSULTS PX1'E INTEGRAL ATTACIHIENT FIELDS llhNOER HAXX!IUi'I SHEAR STRESS ~SAP"TY PACTOR Rii R-R-74 840 463 PSI 39 lniR-Ii-1~ 15940 2155 1'SI 8.3 IOIR-11-3'" 11075 1367 PSI 13. 2 1,"'OAD(POUNDS)
'HS-H-131 P 3606 740 PSX 24.3
-Cl'<
1 IS-I 1-132, 6350 1425 PSI LZ.6
-C2 < I RIIC H 1)'< 1300 854 PSX 21 Ill'CX-il-l 6)06)0 1630 PSI 11.0
(!1152)
Ill'CI-H-2 2368 1071>> PSX 16.8 (I!4>>3)
I!II-Z, -12 "< ll800 1780 PSX 10. l It!I"I, -9:< 13401>> <7>1 10.5 Rli-10, - 1. 89<3<) 134') PS 1 13. 4
~<<')r th )sc lu>>;::, <Ir.:)vi'n>>;s c')I l ot<t Coll I)<.'n<.t.rat.ion 1)1<<: fillet: weld".
BFNP SI 4.6.G Page 372 SEP g< ~98~
KKUEST H)R REEIEP ISI-10 nents: Ultrasonic Calibration Standards Class: lard 2 Function: Ultrasonic calibration for examination of welded canponents.
Test irement: Ultrasonic calibration blocks fabricated to 1974 Edition, Summer 1975 Addenda, of Section XI, INA;2232.
Basis for Belief: Ultrasonic calibration blocks enployed for the .
Brovns Ferry baseline examination were fabricated to the 1971 EQition of Section XI. These blocks will continue to be used for future examinations to ensure the repeatability of data. The pipe blocks have 5'awtooth notches running circumferentially 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 ".9 to 1.5 times the diameter of the pipe examined; and thickness and hole size are according to ASME Section III, Figure IX-3432.1 of the 1971 Edition, Summer 1971 Addenda. Material for all blocks vas the same or equivalent "P" number except as discussed in the attached file note and shown in the mill test report also attached.
Alternate I tion: Future examinations vhich require fabrication of new calibration blocks will be performed using calibration blocks which vill 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..
BFNP SI 4.6.G Page 373 9/29/81 FILE NOTE DETERMINATION OF ACOUSTIC PROPERTIES OF VARIOUS CALIBRATION BLOCKS FOR USE IN IN-SERVICE INSPECTIONS AT BROWNS FERRY NUCLEAR PLANT During recent metallurgical examinations of calibration blocks used for baseline and in-service 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-llC, BF-12C, BF-13, and Automation Industries'ISI 4340 3-inch area amplitude block S.N. 1219 were used to examine materials of different P number. The velocity and attenuation in these blocks were compared to the material they were used to examine as described in the following paragraphs.
Block BF-11C was made from 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-lOC, which is A533 grade B, for sound velocity and attenuation.
Using a Krautkramer type USIP-10W ultrasonic flaw detector, with an Automation Industries'.25 MH , type SFB 3/8-inch effective diameter crystal, three back reflections from the 3.007-inch side of BF-12C were placed at the 3-,
z'-,
and 9-inch locations on the CRT graticule. The crystal was then placed on the 3.992-inch of BF-llC. 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 reflection occurred between 4.000 and 4.050 inches and was interpolated to be 4.025 inches. The second back reflection occurred between 8.000 and 8.100 inches and was interpolated 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.
BFNP SI 4.6.G Page 374 9/29/81 DETERMINATION OF ACOUSTIC PROPERTIES OF VARIOUS CALIBRATION BLOCKS FOR USE IN IN-SERVICE INSPECTIONS AT BROWNS FERRY NUCLEAR PLANT To check attenuation an Automation Industries' MH , type SFB, 3/8-inch effective diameter crystal was placed on the 4-inch Z 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-llC 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 attenuation of 1.5 dB/inch. All three measurements were repeated 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'MH ~ type SFB, 3/8-inch effective diameter crystal, the 100-inch scale of the ultrasonic instrument was checked for linearity 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.
Th e s arne amplitude was obtained on the xeactor closure head stud using 42 dB.
On the basis of the above tests, BF-13 is considered a satisfactory calibrat lo on block for A540 grade B23 material.
The Automation Industries'ISI 4340 3-inch area amplitude block S.N. 1219 is also used for examining recixculation pump nuts made from A194 Cl. 2H material. Both nuts and blocks were 3 inches thick. Both distances measured 3 inches by using the USIP-10W Krautkramer ultrasonic flaw detector with an Automation Industries' MH , type SFB, 3/8-inch effective diameter crystal. Attenuation was checked on the nut by setting the first back reflection to 60 percent of full scale and then bringing the second back reflection up t'o 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.
BFNP SI 4.6.G Page 375 9/29/81 DETERMINATION OF ACOUSTIC PROPERTIES OF VARIOUS CALIBRATION BLOCKS FOR USE IN IN"SERVICE INSPECTION AT BROWNS FERRY NUCLEAR PLANT
~Summar Calibration Block No. Material Attenuation BF-10C A533, Grade B 0. 75 dB/inch BF-llC 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-llC or BF-12C. Therefore, use of BF-12 to calibrate a scope for use in testing A533, grade B, material will result in a test more sensitive than requird 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'ISI 4340 was found to have the same attenuation as the nuts for which it was used as a calibration block.
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- llC A515, Grade 70 Used for nozzle-to-head, head, and nozzle-to-vessel welds Supplied by SwRI after unit 1 inspection Attenuation 2.25 dB/inch BF-12C A515, Grade 55 Used for support skirt welds Attenuation 1.5 dB/inch
BPNP SI 4.6.G Page 376 9/29/81 DETERMINATION OF ACOUSTIC PROPERTIES OF VARIOUS CALIBRATION BLOCKS FOR USE IN IN-SERVICE INSPECTIONS AT BROMNS FERRY NUCLEAR PLANT Descri tion of the Blocks continued:
BF-13 Crucible. 422 Used for 65.5-inch studs Attenuation same as studs Automation Industries'ISI 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.
COMBUSTION ENGINEERING, INC.
TVA BROWNS PERRY ULTRASONIC CALIBRATION BLOCKS TVA CE Elements Identif. Identif. Ni Cr Mo Comments BF-lc P-14607 0. 240 0. 96 0. 013 0. 016 0. 21 <0. 010 <0. 01 <0. 01 0. 001 A106, Gr. B BF-2S P-14608 0. 03.5 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 l. 66 0. 032 0. 016 0. 41 9.600 18. 54 0. 28 0. 040
<0. 001 A358, 304 SS BF-5C P-14611 0. 250 0. 85 0. 003 0. 022 0. 17 0. 030. 0. 01 <0. Ol A106, Gr. B BF-6S P-14612 0. 053 1. 60 0. 021 0. 018 0. 52 10.470 18. 37 0. 17 0. 050 A358$ 304 SS BF-7C P-14613 0. 260 0. 90 0. 004 0. 020 0. 13 <0.010 <0. Ol <0. Ol <0. 001 A106, Gr. B BF-8S P-14614 0. 035 1. 60 0. 020 0. 009 0. 53 8.510 19. 17 0. 19 0. 040 A240, 304 SS BF-9C P-14615 0. 230 0. 92 0. 007 0. 017 0. 02 0.010 <0.01 <0. 01 <0. 001 A36 (A283)
BF-10C P-14616 0. 230 l. 22 0. 010 0. 015 0. 22 0.470 0.09 0. 49
<0. 01
<0. 003 A533, Gr. B BF-llC P-14617 0. 330 0. 74 0. 008 0. 023 0. 21 0.070 0. 02 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 ll.19 0. 93 0. 250 A437, Gr. B4C BF-15C P-14620 0. 210 0. 44 0. 013 0. 021 0. 11 0. 020 <0.01 <0. Ol <0. 001 A519, Gr. MT 1000
-m&te&
WC) HM M 00 R. A. Nation we c w 00 IA W Metallurgical Engineer P'V~
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BFNP Sr <.6.G Page 378
~RE VEST FOR RELIEF ISI-11 SEP 29 l981
~Ss tern: Main steam Class:
Test Requirement: Surface examination of support members for piping examination category C-E-l.
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, and they will be surface examined
~
during the inspection intervals (see attached drawings).
Altetnate In~section: Xone.
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SI 4.6.G Page 381 ill'A/III;SI'<0lt Ri;I,TI'.I'SI-12 SEP 29 'f981 I
!Iys tc m: Rusk<I<<al iicat Removal an(l ?!ain St:cern Class:
< I c ( I<< i r"".i >>r ",<< 'in<<r <
~ ('. I',xal<n: <ur t' <)r< (If I'1'i'ssu t e-Rcta ininf,
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I'nr R< I i. i "<'h(re< i<<r:<. E!IR .Ion(:it<<<I!n:il pii>e weld (a(Ijoinir'.;.;
<:irctrmfcrcrrtial weld I).'(III<-3-13) an<i one main stcam loll!','I t<l<l inn l, p ipc weld (;i<i'jo i<ring circumferential vcl<l C?!S-3-2) wlricir are pac't tally inaccessible for irtsc.rvicc- examination. Tl>cse wclds are located lrtni<lc (:nrrtninmcnt'. pen<.trot iona. Approximately 6 inchc.s of tire R!IR weld a<<d 2 inches of the main stcam wel<l arc accessible for inservice examination.
In a<I<lit!on, there is one nrain stcam longitudinal pipe veld (a(ljoining circumf ore.ntial welds CHS-3-3 and AlS-3-1) which is Located under a perman<.nt restraint (sec Request for Relief ISI-7).
Approxi<nar:r ly 6 inches of this weld is accessible for inscrvice examination.
Alterna t <. Innpec t ion: None
BFNP SI 4. 6.G Page 382 SEI'29 ~98>
Request For Rcl ief 181-13 Colnl)on<<lit s RllR licat Exchangcrs - iiiiits 1,, and
(:1:i Fil lie t i on Prcssure rct;iinini: noxzlc wi l(ls i>> vcss( is
~
1 cii t R<<igni Yclllclit: Volumetric cx;imin:it ion oi'ioxxlc-Lo-v(sscl attaclimcnt i"olds, examinat.ion <<:iti gory C-l3 Bas is i'or Rc lief: Tlie RliR heat cxclianiti rs noxxl t-to-vcss<<1 hatt'aclunent weld is covered by,i rcinfi rri.ment ring (shown in tile atrarlic<1 sketch) wliicli iliics not. al low iccess to any of tlie att;i<<limcnr veld. P Al t.crn:tte ~Itis iect ion: Tlie reinforcement ri>>g wclds arc acces:"ible aiitl will bc given a surface examinatLon. Two reinforcement rings on each unit wi 11 bt examined over the 40-year insPect ion intcrv;il in accordance wi tli TWC-2411 on rhSilE Section yl.
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TENNESSEE YAI.LEY AUTHORITY DIYISlON OF NUCLEAR POWER R H R HEAT EXCHANGER REtNFQRCEMj.NT. RlNG 'TELOS
BFNP SI 4.6.G Page 384, SEP 29 i981 Rl:.QUI ST FOR REI.II:F ISI-14 1'rcssurc-retaining bol4, inI; Class:
Yisual, surface, and volumetric examination of prcssure-retaining bolting exceeding one inch In diamctcr, examination category C-I).
Basis for Rcl.ief: Examination of class 2 pressure-retaining bolting in accordance vith thc Summer 1975 hd<l coda of Sect ion XI excccds inspac t ion requirements for class 1 pressure-retaining bolting. We do not feel an increased level of safety is obtained from a mora restrictive examination of class 2 components.
hn examination program for class 2 pres.,ure-retaining bolting similar. to that for class 1 should be desirable. This type of examination has been incorpo~ atcd in the 1977 Edition, Summer 197S and Summer 1979 Addenda of Section XX, which Browns Ferry may be required to meet in thc future.
Alt ornate liana
~action: Cla..s 2 pressurc-retaining bolting exceeding two inches in diameter shall be volumetrically examined in accordance with Table IWC-2500-1, examination ca tegory C-9 of the 1977 Edition, Summer ]979 h<ldenda of Section XI. Prassure-reI:aining bolting two inches or less in diameter will not Iie examined.
BFNP SI 4.6.G Page 385 SEP 29 198[
REQUEST 83R REt'IEF ISI-15 nents: Ultrasonic examination technique of piping welds.
land 2 Function: Ultrasonic calibration and examination of welded piping ccmponents.
Test irement: 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) piping welds is being updated to the 1977 Edition, Summer 1978 Addenda of ASME Section XI to provide state-of-the-art methcds for both. Were are existing requests for 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.
We 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 Ins tion: As specified jp ISI-8 and XSI-10.
i